WorldWideScience

Sample records for range safety annual

  1. 2011 NASA Range Safety Annual Report

    Science.gov (United States)

    Dumont, Alan G.

    2012-01-01

    Welcome to the 2011 edition of the NASA Range Safety Annual Report. Funded by NASA Headquarters, this report provides a NASA Range Safety overview for current and potential range users. As is typical with odd year editions, this is an abbreviated Range Safety Annual Report providing updates and links to full articles from the previous year's report. It also provides more complete articles covering new subject areas, summaries of various NASA Range Safety Program activities conducted during the past year, and information on several projects that may have a profound impact on the way business will be done in the future. Specific topics discussed and updated in the 2011 NASA Range Safety Annual Report include a program overview and 2011 highlights; Range Safety Training; Range Safety Policy revision; Independent Assessments; Support to Program Operations at all ranges conducting NASA launch/flight operations; a continuing overview of emerging range safety-related technologies; and status reports from all of the NASA Centers that have Range Safety responsibilities. Every effort has been made to include the most current information available. We recommend this report be used only for guidance and that the validity and accuracy of all articles be verified for updates. Once again the web-based format was used to present the annual report. We continually receive positive feedback on the web-based edition and hope you enjoy this year's product as well. As is the case each year, contributors to this report are too numerous to mention, but we thank individuals from the NASA Centers, the Department of Defense, and civilian organizations for their contributions. In conclusion, it has been a busy and productive year. I'd like to extend a personal Thank You to everyone who contributed to make this year a successful one, and I look forward to working with all of you in the upcoming year.

  2. Prediction ranges. Annual review

    Energy Technology Data Exchange (ETDEWEB)

    Parker, J.C.; Tharp, W.H.; Spiro, P.S.; Keng, K.; Angastiniotis, M.; Hachey, L.T.

    1988-01-01

    Prediction ranges equip the planner with one more tool for improved assessment of the outcome of a course of action. One of their major uses is in financial evaluations, where corporate policy requires the performance of uncertainty analysis for large projects. This report gives an overview of the uses of prediction ranges, with examples; and risks and uncertainties in growth, inflation, and interest and exchange rates. Prediction ranges and standard deviations of 80% and 50% probability are given for various economic indicators in Ontario, Canada, and the USA, as well as for foreign exchange rates and Ontario Hydro interest rates. An explanatory note on probability is also included. 23 tabs.

  3. Range Flight Safety Requirements

    Science.gov (United States)

    Loftin, Charles E.; Hudson, Sandra M.

    2018-01-01

    The purpose of this NASA Technical Standard is to provide the technical requirements for the NPR 8715.5, Range Flight Safety Program, in regards to protection of the public, the NASA workforce, and property as it pertains to risk analysis, Flight Safety Systems (FSS), and range flight operations. This standard is approved for use by NASA Headquarters and NASA Centers, including Component Facilities and Technical and Service Support Centers, and may be cited in contract, program, and other Agency documents as a technical requirement. This standard may also apply to the Jet Propulsion Laboratory or to other contractors, grant recipients, or parties to agreements to the extent specified or referenced in their contracts, grants, or agreements, when these organizations conduct or participate in missions that involve range flight operations as defined by NPR 8715.5.1.2.2 In this standard, all mandatory actions (i.e., requirements) are denoted by statements containing the term “shall.”1.3 TailoringTailoring of this standard for application to a specific program or project shall be formally documented as part of program or project requirements and approved by the responsible Technical Authority in accordance with NPR 8715.3, NASA General Safety Program Requirements.

  4. Annual Safety Report 1981

    International Nuclear Information System (INIS)

    1982-09-01

    A safety report from Section K (Nuclear Physics) of the Dutch National Institute for Nuclear and High Energy Physics is presented for 1981. The report begins with general matters concerning safety policy at NIKHEF, licences and expenditure. Works accidents (none of them radiological) are detailed and accident prevention considered. The measurement programme for neutron radiation in the vicinity of the accelerator is described and the results are discussed. The means and results of personnel dosimetry are also presented. The report is concluded with a list of publications concerning safety aspects at NIKHEF. (C.F.)

  5. Autonomous system for launch vehicle range safety

    Science.gov (United States)

    Ferrell, Bob; Haley, Sam

    2001-02-01

    The Autonomous Flight Safety System (AFSS) is a launch vehicle subsystem whose ultimate goal is an autonomous capability to assure range safety (people and valuable resources), flight personnel safety, flight assets safety (recovery of valuable vehicles and cargo), and global coverage with a dramatic simplification of range infrastructure. The AFSS is capable of determining current vehicle position and predicting the impact point with respect to flight restriction zones. Additionally, it is able to discern whether or not the launch vehicle is an immediate threat to public safety, and initiate the appropriate range safety response. These features provide for a dramatic cost reduction in range operations and improved reliability of mission success. .

  6. Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 1995

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1996-09-01

    The scientific work of the Institute of Safety Research covers a wide range of safety related investigations. During 1995 important results on thermo-fluid dynamic single effects, thermalhydraulics and neutron kinetics for accident analysis, materials safety, simulation of radiation and particle transport, mechanical integrity of technical systems and process monitoring, risk management for waste deposits, magneto-hydrodynamics of conductive fluids, and of renewable energies were reached. The annual report presents also lists of publications, conference contributions, meetings, and workshops. (DG)

  7. Annual report on occupational safety

    International Nuclear Information System (INIS)

    1985-09-01

    A report is given on the occupational safety relating to BNFL's employees for the year 1984 and the results compared to those obtained in 1983. Data are presented for each of the Company's Sites on whole body exposures, accidental deaths and major injuries and nuclear and non-nuclear incidents. The results show that the Company average body dose continues to be less than 5mSv, there were no accidental deaths but 15 major injuries. One nuclear incident and 9 non-nuclear incidents were notified to the Health and Safety Executive. (UK)

  8. Health and safety annual report 1992

    International Nuclear Information System (INIS)

    1993-01-01

    BNFL operates 6 sites in the United Kingdom concerned with the nuclear fuel cycle. The annual report on occupational health and safety gives information on all aspects of health and safety within BNFL with special reference to radiation doses received by the workforce and radiation protection measures taken by the company. BNFL's safety policy is set out. Radiation doses to all workers have remained low. Other industrial accidents are also listed and its safety measures for transport, radioactive effluents and in the event of an incident, are mentioned briefly. (UK)

  9. 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)

  10. Nuclear Safety Project - annual report 1980

    International Nuclear Information System (INIS)

    1981-08-01

    The Annual Report 1980 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1980 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work completed, essential results, plans for the near future. (orig./RW) [de

  11. Nuclear safety research project. Annual report 1995

    International Nuclear Information System (INIS)

    Hueper, R.

    1996-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1995 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1996. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  12. Nuclear Safety Project. Annual report 1983

    International Nuclear Information System (INIS)

    1984-06-01

    The annual report 1983 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1983 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig.) [de

  13. Nuclear safety project. Annual report 1985

    International Nuclear Information System (INIS)

    1986-07-01

    The annual report 1985 is a detailed description (in German language) of work within the nuclear safety project performed in 1985 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./HP) [de

  14. Annual report on occupational safety 1983

    International Nuclear Information System (INIS)

    1984-08-01

    The 1983 Annual Report on occupational safety at BNFL is presented. Data for whole-body radiation doses and skin and extremity doses are given for BNFL employees together with 1982 data for comparison. Similarly, accidental deaths and major injuries are recorded. Finally information on the frequency of both nuclear and non-nuclear incidents reported to the Health and Safety Executive is given. (U.K.)

  15. Health and safety annual report 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This 1989 annual report on Health and Safety in BNFL is intended to give the public a general review of the impact of the Company's activities on its workforce, the public and the environment. The activities at Sellafield, Springfields, Chapelcross, Drigg and Capenhurst are outlined, together with sections on medical services and transport, and radiation monitoring of workforce and the environment. (author)

  16. Annual report ''nuclear safety in France''

    International Nuclear Information System (INIS)

    2001-01-01

    This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

  17. 78 FR 5866 - Pipeline Safety: Annual Reports and Validation

    Science.gov (United States)

    2013-01-28

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID PHMSA-2012-0319] Pipeline Safety: Annual Reports and Validation AGENCY: Pipeline and Hazardous Materials... 2012 gas transmission and gathering annual reports, remind pipeline owners and operators to validate...

  18. Nuclear Safety Project. Annual report 1986

    International Nuclear Information System (INIS)

    1987-09-01

    The annual report 1986 is a detailed description of work within the Nuclear Safety Project performed in 1986 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes individual research activities on dynamic loads and strains of reactor components under accident conditions, fuel behaviour under accident conditions, investigation and control of LWR core-meltdown accidents, improvement of fission product retention and reduction of radiation exposure, and on behaviour, impact and removal of released pollutants. (DG)

  19. Annual safety research report, JFY 2012

    International Nuclear Information System (INIS)

    2013-08-01

    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 (5 subjects and each subject having several research projects totaled 20), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 6), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), 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 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). In addition to these 49 research projects of 18 subjects in 6 areas, JNES worked on 19 research projects of 7 subjects in added areas (specific research projects on of the disaster at Fukushima Daiichi NPP accident and other challenges JNES considered necessary) in JFY 2012. This annual safety research report summarized respective achievements and state of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2012 Edition as well as the situation of the reflection for the safety regulations, and also described 16 research projects of 4 subjects: examination for new safety regulation (8 research projects), development of newly necessary evaluation methods (one research project), evaluation of the validity for the work for convergence at Fukushima Daiichi NPP accident (4 research project) and horizontal development to other nuclear power plants (3 research projects), and 3 research projects of 3 subjects as other challenges. A list of JNES

  20. Institute for Safety Research. Annual report 1992

    International Nuclear Information System (INIS)

    Weiss, F.P.; Boehmert, J.

    1993-11-01

    The Institute is concerned with evaluating the design based safety and increasing the operational safety of technical systems which include serious sources of danger. It is further occupied with methods of mitigating the effects of incidents and accidents. For all these goals the institute does research work in the following fields: modelling and simulation of thermofluid dynamics and neutron kinetics in cases of accidents; two-phase measuring techniques; safety-related analyses and characterizing of mechanical behaviours of material; measurements and calculations of radiation fields; process and plant diagnostics; development and application of methods of decision analysis. This annual report gives a survey of projects and scientific contributions (e.g. Single rod burst tests with ZrNb1 cladding), lists publications, institute seminars and workshops, names the personal staff and describes the organizational structure. (orig./HP)

  1. 2011 Annual Criticality Safety Program Performance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The

  2. Safety assessment of outdoor live fire range

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-05-01

    The following Safety Assessment (SA) pertains to the outdoor live fire range facility (LFR). The purpose of this facility is to supplement the indoor LFR. In particular it provides capacity for exercises that would be inappropriate on the indoor range. This SA examines the risks that are attendant to the training on the outdoor LFR. The outdoor LFR used by EG&G Mound is privately owned. It is identified as the Miami Valley Shooting Grounds. Mondays are leased for the exclusive use of EG&G Mound.

  3. TIS General Safety Group Annual Report 2000

    CERN Document Server

    Weingarten, W

    2001-01-01

    This report summarises the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division (TIS) during the year 2000, and the results obtained. The different topics in which the Group is active are covered: general safety inspections and ergonomy, electrical, chemistry and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

  4. Annual report on occupational safety 1985

    International Nuclear Information System (INIS)

    1986-09-01

    This report presents information on occupational safety relating to the Company's employees for the year 1985, and compares data with figures for the previous year. The following headings are listed: principle activities of BNFL, general policy and organisation, radiological safety, including whole body, skin and extremity, and internal organ doses, non-radiological safety, incidents reportable to the health and safety executive. (U.K.)

  5. FAA National Aviation Safety Inspection Program. Annual Report FY90

    Science.gov (United States)

    1991-06-01

    This report was undertaken to document, analyze, and place : into national perspective the findings from the 1990 National : Aviation Safety Inspection Program (NASIP). This report is the : fifth in a series of annual reports covering the results of ...

  6. Transit safety & security statistics & analysis 2002 annual report (formerly SAMIS)

    Science.gov (United States)

    2004-12-01

    The Transit Safety & Security Statistics & Analysis 2002 Annual Report (formerly SAMIS) is a compilation and analysis of mass transit accident, casualty, and crime statistics reported under the Federal Transit Administrations (FTAs) National Tr...

  7. Transit safety & security statistics & analysis 2003 annual report (formerly SAMIS)

    Science.gov (United States)

    2005-12-01

    The Transit Safety & Security Statistics & Analysis 2003 Annual Report (formerly SAMIS) is a compilation and analysis of mass transit accident, casualty, and crime statistics reported under the Federal Transit Administrations (FTAs) National Tr...

  8. Priming patient safety: A middle-range theory of safety goal priming via safety culture communication.

    Science.gov (United States)

    Groves, Patricia S; Bunch, Jacinda L

    2018-05-18

    The aim of this paper is discussion of a new middle-range theory of patient safety goal priming via safety culture communication. Bedside nurses are key to safe care, but there is little theory about how organizations can influence nursing behavior through safety culture to improve patient safety outcomes. We theorize patient safety goal priming via safety culture communication may support organizations in this endeavor. According to this theory, hospital safety culture communication activates a previously held patient safety goal and increases the perceived value of actions nurses can take to achieve that goal. Nurses subsequently prioritize and are motivated to perform tasks and risk assessment related to achieving patient safety. These efforts continue until nurses mitigate or ameliorate identified risks and hazards during the patient care encounter. Critically, this process requires nurses to have a previously held safety goal associated with a repertoire of appropriate actions. This theory suggests undergraduate educators should foster an outcomes focus emphasizing the connections between nursing interventions and safety outcomes, hospitals should strategically structure patient safety primes into communicative activities, and organizations should support professional development including new skills and the latest evidence supporting nursing practice for patient safety. © 2018 John Wiley & Sons Ltd.

  9. KIT safety management. Annual report 2012

    International Nuclear Information System (INIS)

    Frank, Gerhard

    2013-01-01

    The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

  10. Annual report on occupational safety 1987

    International Nuclear Information System (INIS)

    1988-01-01

    This report presents detailed information on occupational safety relating to the Company's employees for 1987. Data are quoted in tables and text, together with data from the previous year for comparison where available. The report is presented under the following headings: radiological and non-radiological safety, incidents, appendices (statutory dose limits, nuclear incident criteria for reporting to ministers). (author)

  11. Annual report on occupational safety 1989

    International Nuclear Information System (INIS)

    1990-01-01

    This report presents detailed information on occupational safety relating to BNFL's employees for 1989 and data compared with the previous year. Routine monitoring, non-radiological safety and 'incidents' are discussed and 'statutory' whole-body exposures, nuclear incidents, lost-time accidents, and types of injury are tabulated. (author)

  12. Nuclear Safety Research Department annual report 2000

    DEFF Research Database (Denmark)

    Majborn, B.; Nielsen, Sven Poul; Damkjær, A.

    2001-01-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addtion the department...

  13. Nuclear Safety Research Department annual report 2001

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Nielsen, Sven Poul

    2002-01-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2001. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addition the department...

  14. Safety and health annual report 1996

    International Nuclear Information System (INIS)

    1997-01-01

    The 1996 report on the Health and Safety performance of the nuclear fuel cycle company BNFL at its sites in the United Kingdom demonstrates a continuing improvement. The site locations and developments are briefly described and international developments in subsidiary organisations noted. Other sections of the report cover health and safety policy, radiological and industrial safety, emergency planning, incidents, occupational health services, compensation scheme developments, transport, putting radiation in perspective, and safety and health research. Data are provided on: radioactive discharges; industrial safety of BNFL and contractors' employees; radiation dose summaries for BNFL and contractors' employees. There is evidence of the expected plateauing out of doses to BNFL employees at a level less than or similar to background radiation. (UK)

  15. Safety-related LWR research. Annual report 1993

    International Nuclear Information System (INIS)

    Hueper, R.

    1994-06-01

    The reactor safety R and D work of the Karlsruhe Nuclear Research Centre (KfK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1993 summarizes the results on LWR safety. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status at the end of 1993. (orig./HP) [de

  16. Health and safety annual report 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The principal activities and organisation of BNFL are reviewed in relation to the impact these activities have on the workforce, members of the general public and the environment, together with services for occupational safety within the company. (author)

  17. Health and safety annual report 1988

    International Nuclear Information System (INIS)

    1989-01-01

    This report on health and safety provides a review of the impact of the Comapny's activities on its workforce, the public and the environment. New sections include safety auditing, emergency planning and health and safety research. BNFL operates five sites in north west England and southern Scotland. The head office and Engineering Design Centre is at Risley, near Warrington. Fuel is manufactured at Springfields near Preston, uranium is enriched for modern nuclear power stations at Capenhurst near Chester and spent fuel is reprocessed at Sellafield. BNFL also operate Calder Hall (Sellafield) and Chapelcross (Scotland) power stations and a disposal site for low-level radioactive wastes at Drigg near Sellafield. Radiation sources and BNFL's radioactive discharge are first explained generally and then specifically for each BNFL site. Industrial and radiological safety within BNFL are described. (UK)

  18. Health and Safety annual report 1993

    International Nuclear Information System (INIS)

    1994-01-01

    In the 1993 Health and Safety Report for BNFL, data showing improvements in radiological and conventional safety are given. Other aspects discussed are emergency planning, the level of incidents, occupational health services, litigation and the compensation scheme, the transport of radioactive materials, research covering transgenerational epidemiology, mortality and cancer studies, genetics and radiobiology, and dosimetry, and finally a summary of radioactive discharges and environmental data. (UK)

  19. Nuclear Safety Research Department annual report 2000

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E.

    2001-08-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

  20. Central Safety Department. Annual report 1986

    International Nuclear Information System (INIS)

    Kiefer, H.; Koenig, L.A.

    1987-03-01

    The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Central Safety Department. The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. The report gives details of the different duties, indicates the results of 1986 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

  1. Annual Report 1979 of the Safety Department

    International Nuclear Information System (INIS)

    Kiefer, H.; Koelzer, W.; Koenig, L.A.

    1980-04-01

    The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implemantation of nuclear fuel safeguarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1979 routine tasks, and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

  2. 1978 annual report of the safety department

    International Nuclear Information System (INIS)

    Kiefer, H.; Koelzer, W.

    1979-04-01

    The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assitance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implementation of nuclear fuel safequarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1978 routine tasks, and reports about new results of investigations and developments of the working groups of the Department. (orig.) [de

  3. Fusion Safety Program. Annual report, FY 1982

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1983-07-01

    The Fusion Safety Program major activities for Fiscal Year 1982 are summarized in this report. The program was started in FY-79, with the Idaho National Engineering Laboratory (INEL) designated as lead laboratory and EG and G Idaho, Inc., named as prime contractor to implement this role. The report contains four sections: EG and G Idaho, Inc., Activities at INEL includes major portions of papers dealing with ongoing work in tritium implantation experiments, tritium risk assessment, transient code development, heat transfer and fluid flow analysis, and high temperature oxidation and mobilization of structural material experiments. The section Outside Contracts includes studies of superconducting magnet safety conducted by Argonne National Laboratory, experiments concerning superconductor safety issues performed by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) to verify analytical work, a continuation of safety and environmental studies by MIT, a summary of lithium safety experiments at Hanford Engineering Development Laboratory, and the results of tritium gas conversion to oxide experiments at Oak Ridge National Laboratory. A List of Publications and Proposed FY-83 Activities are also presented

  4. Central Safety Department, annual report 1987

    International Nuclear Information System (INIS)

    Kiefer, H.; Koenig, L.A.

    1988-02-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behaviour of biologically particularly active radionuclides, behaviour of HT in the air/plan/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1987 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig./HP) [de

  5. Nuclear Safety Research Department annual report 2000

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E

    2001-08-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

  6. 1982 annual status report: reactor safety

    International Nuclear Information System (INIS)

    1982-01-01

    This report presents the projects of the Reactor Safety Program at the JRC: 1) Reliability and risk evolution; 2) LWR loss of coolant accident studies; 3) Primary system integrity; 4) LMFBR core accident initiation and transition phase; and, 5) LMFBR accident post disassembly phase

  7. Safety oriented LWR research. Annual report 1990

    International Nuclear Information System (INIS)

    1991-07-01

    The contributions describe phenomenons of severe fuel damage and aspects of core meltdown accidents. These accidents deal with aerosol behaviour and ventilation systems and the methods for assessing and reducing the radiological concequences of nuclear accidents. Other contributions describe selected questions of safety of HCLWR type reactors. (DG)

  8. Annual colloquium 1976 of the project nuclear safety

    International Nuclear Information System (INIS)

    1976-11-01

    The present report gives the full text of the nine papers read during the annual colloquium 1976 of the Project Nuclear Safety at Karlsruhe Nuclear Research Centre, in which the main activities and findings of the project in 1976 are contained. (RW) [de

  9. Proceedings of the first annual Nuclear Criticality Safety Technology Project

    International Nuclear Information System (INIS)

    Rutherford, D.A.

    1994-09-01

    This document represents the published proceedings of the first annual Nuclear Criticality Safety Technology Project (NCSTP) Workshop, which took place May 12--14, 1992, in Gaithersburg, Md. The conference consisted of four sessions, each dealing with a specific aspect of nuclear criticality safety issues. The session titles were ''Criticality Code Development, Usage, and Validation,'' ''Experimental Needs, Facilities, and Measurements,'' ''Regulation, Compliance, and Their Effects on Nuclear Criticality Technology and Safety,'' and ''The Nuclear Criticality Community Response to the USDOE Regulations and Compliance Directives.'' The conference also sponsored a Working Group session, a report of the NCSTP Working Group is also presented. Individual papers have been cataloged separately

  10. Health, safety and environment : annual report 2000

    International Nuclear Information System (INIS)

    2000-01-01

    A natural gas transmission and power services company, TransCanada Pipelines Limited operates approximately 38,000 kilometers of pipeline, thereby supplying the majority of natural gas production facilities in Western Canada. The company is also involved in the power generation industry by building, operating and owning interests in electric power plants. Located in Rhode Island, United States, the largest plant operated by TransCanada is a combined-cycle plant that generates in excess of 500 MW. TransCanada is committed to its health, safety and environment management system. The system is modeled after the elements of the International Organization for Standardization (ISO) 14001 which sets the standard for environmental management systems. Considerable efforts were expanded to implement programs and initiatives to protect the environment, such as the pipeline reclamation criteria, the hazardous materials and waste management, and proposed polychlorinated biphenyl (PCB) regulations, which are currently under consideration by Environment Canada. TransCanada PipeLines Limited has also set up an environmental research program to enable management and workers to minimize the environmental impacts of the business. Its objectives are the enhancement of the health and safety of employees and their communities, the mitigation of effects on lands, air and water. The topics covered by the research are: vegetation and wildlife with several sub-categories. The company is concerned about the effects on climate change, and developed plans and strategies to manage the emissions of greenhouse gases. In the process, it was awarded several awards for its commitment, action and leadership on voluntary reduction program of greenhouse gases. Full-time resources are dedicated to illness prevention and health promotion, employee assistance programs, short and long term disability management and others. During the year 2000, TransCanada invested 4 million dollars in communities

  11. 1980 Annual status report reactor safety

    International Nuclear Information System (INIS)

    1981-01-01

    The JRC reactor safety programme involves theoretical and experimental activities to analyse accidents and their consequences for LWRs and LMFBRs. The first project deals with the improvement and the application of methodologies for risk and reliability assessment. This activity involves the identification and modelling of accident sequences and events and the analysis of fault trees. In this project, the implementation of a centralized data bank system (European Reliability Data System) is foreseen, which should provide the information needed for risk assessment studies. In project 2 a major effort on LWRs is centered on the study of the loss-of-coolant accident following large, intermediate or small breaks of the primary circuit. These accidents are simulated out of pile in the LOBI facility. In project 3 a contribution is made to solve material problems and to provide data and calculation methods for end of life predictions of reactor components. It involves a contribution to the programme for the inspection of steel components (PISC) as well as the study of fracture and creep fatigue properties of stainless steel. In the project 4 and 5 a deterministic approach is adopted to solve some problems of large hypothetical accidents in an LMFBR. The calculation tools developed concern sodium thermohydraulics in fuel element bundles, fuel coolant interaction, whole core accident analysis, containment loading and response and post accident heat removal

  12. Forage selection and performance of sheep grazing dry annual range.

    NARCIS (Netherlands)

    Ridder, de N.; Benjamin, R.W.; Keulen, van H.

    1986-01-01

    During 114 days of grazing, sheep grazing a dry annual pasture in Israel selected the fine fraction available with a higher nutritive value. As this fraction became depleted and feed quality dropped, organic matter intake dropped from 1.73 to 0.75 kg/sheep/d. Sheep lost weight, body condition and

  13. Institutional glovebox safety committee (IGSC) annual report FY2010

    Energy Technology Data Exchange (ETDEWEB)

    Cournoyer, Michael E [Los Alamos National Laboratory; Roybal, Richard F [Los Alamos National Laboratory; Lee, Roy J [Los Alamos National Laboratory

    2011-01-04

    The Institutional Glovebox Safety Committee (IGSC) was chartered to minimize and/or prevent glovebox operational events. Highlights of the IGSC's third year are discussed. The focus of this working committee is to address glovebox operational and safety issues and to share Lessons Learned, best practices, training improvements, and glovebox glove breach and failure data. Highlights of the IGSC's third year are discussed. The results presented in this annual report are pivotal to the ultimate focus of the glovebox safety program, which is to minimize work-related injuries and illnesses. This effort contributes to the LANL Continuous Improvement Program by providing information that can be used to improve glovebox operational safety.

  14. Nuclear safety research project (PSF). 1999 annual report

    International Nuclear Information System (INIS)

    Muehl, B.

    2000-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report summarizes the R and D results of PSF during 1999. The research tasks cover three main topics: Light Water Reactor safety, innovative systems, and studies related to the transmutation of actinides. The importance of the Light Water Reactor safety, however, has decreased during the last year in favour of the transmutation of actinides. Numerous institutes of the research centre contribute to the PSF programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2000. (orig.) [de

  15. Safety-related LWR research. Annual report 1989

    International Nuclear Information System (INIS)

    1990-11-01

    The main topics in this annual report 1989 are phenomena of heavy fuel damage and single aspects of a core meltdown accident. The examined single aspects refer to aerosol behavior and filter engineering and to methods for assessment and minimization of the radiological consequences of reactor accidents. Different contributions to selected, safety-related problems of an advanced pressurized-water reactor complete the topic spectrum. The annual report 1989 describes the progress of the research work wich was carried out in the area of safety research by institutes and departments of the KfK, and on behalf of the KfK by external institutions. The individual contributions represent the status of work at the end of the year under review, 1989. (orig./HP) [de

  16. 76 FR 7131 - Safety Zones; Eleventh Coast Guard District Annual Fireworks Events

    Science.gov (United States)

    2011-02-09

    ...-AA00 Safety Zones; Eleventh Coast Guard District Annual Fireworks Events AGENCY: Coast Guard, DHS... permanent safety zones to ensure public safety during annual firework displays at various locations in the... events, delete events that are no longer occurring, add new unlisted annual fireworks events to the...

  17. Annual report 1986 of Society for Reactor Safety (GRS)

    International Nuclear Information System (INIS)

    1987-01-01

    The overall development of Society for Reactor Safety (GRS) is indicated by its annual volume of achievement. After initially high growth rates that achievement has come to stand at some 62 million marks or so over the last years. GRS today employs some 450 staff, of which 325 are scientific-technical experts representing altogether nearly 4000 man-years of experience in nuclear technology. The report presents essential results from the main points of activity of GRS over 10 years. In accordance with the aim of the institution they primarily cover projects in the sectors safety and radiation protection for nuclear facilities. Since 1985, since the extension of its contract of associates, GRS has also increasingly been concerned with safety questions in non-nuclear technology, concentrating mainly on the transfer of existing methods. (orig./DG) [de

  18. IRSN - Annual Report 2013. Financial Report 2013. Enhancing nuclear safety

    International Nuclear Information System (INIS)

    Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Aurelle, Jacques; Bigot, Marie-Pierre; Bruna, Giovanni; Charron, Sylvie; Clavelle, Stephanie; Cousinou, Patrick; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Dumas, Agnes; Franquard, Dominique; Laloi, Patrick; Lorthioir, Stephane; Monti, Pascale; Rollinger, Francois; Rouyer, Veronique; Rutschkovsky, Nathalie; Scott De Martinville, Edouard; Tharaud, Christine; Verpeaux, Jean-Luc; Jaunet, Camille; Hedouin, Jean-Christophe; Pascal-Heuze, Charlotte

    2014-03-01

    , Organization chart and Executive committee, Board of directors, Steering committee for the nuclear defense expertise division - CODEND composition, Scientific council, Ethics commission composition, Nuclear safety and radiation protection research policy committee - COR; 5 - Glossary; 6 - Financial report: management report, financial statements, appendix to the annual accounts

  19. Enhancing nuclear safety. Annual report 2014. Financial report 2014

    International Nuclear Information System (INIS)

    2015-01-01

    After some introductory texts proposed by several IRSN head managers, and a brief presentation of some key data illustrating the activity, the annual report presents the main strategic orientations, notably in the field of knowledge management, and of information and communication. After some images illustrating the past year, activities are presented. They first deal with safety: Reactor safety (operating experience feedback), From decommissioning old reactors to designing those of the future, Safety of laboratories and plants, Safety regarding risks due to infrastructure near nuclear facilities, Reactor aging, Fuel: research on corrosion and deformation, Research and assessments for improved understanding of accident situations, Earthquakes: research and assessments, About defense, Geological disposal of radioactive waste. They secondly deal with security and non-proliferation (nuclear security, nuclear non-proliferation, chemical weapon ban), thirdly with radiation protection for human and environment health (environment monitoring, radionuclide transfer in the environment, radon and polluted sites, human exposure, radiation protection in the workplace, effects of low-dose chronic exposures, Organization of radiation protection at the European level, protection in health care), and fourthly with emergency and post-accident situations (emergency and post-accident preparedness and response, Emergency response tools). The next part of the activity report addresses issues related to efficiency: Real estate program (construction projects get started), Hygiene, safety, social responsibility, Human resources, Organization chart, Board of directors, Steering committee for the nuclear defense expertise Division - CODEND, Scientific council, Ethics commission composition, Nuclear safety and radiation protection Research policy committee - COR. The financial report proposes a management report, financial statements with an appendix to annual accounts, and an auditor

  20. 2011 Annual Meeting of the Safety Pharmacology Society: an overview.

    Science.gov (United States)

    Cavero, Icilio

    2012-03-01

    The keynote address of 2011 Annual Meeting of the Safety Pharmacology Society examined the known and the still to be known on drug-induced nephrotoxicity. The nominee of the Distinguished Service Award Lecture gave an account of his career achievements particularly on the domain of chronically instrumented animals for assessing cardiovascular safety. The value of Safety Pharmacology resides in the benefits delivered to Pharma organizations, regulators, payers and patients. Meticulous due diligence concerning compliance of Safety Pharmacology studies to best practices is an effective means to ensure that equally stringent safety criteria are applied to both in-licensed and in-house compounds. Innovative technologies of great potential for Safety Pharmacology presented at the meeting are organs on chips (lung, heart, intestine) displaying mechanical and biochemical features of native organs, electrical field potential (MEA) or impedance (xCELLigence Cardio) measurements in human induced pluripotent stem cell-derived cardiomyocytes for unveiling cardiac electrophysiological and mechanical liabilities, functional human airway epithelium (MucilAir™) preparations with unique 1-year shelf-life for acute and chronic in vitro evaluation of drug efficacy and toxicity. Custom-designed in silico and in vitro assay platforms defining the receptorome space occupied by chemical entities facilitate, throughout the drug discovery phase, the selection of candidates with optimized safety profile on organ function. These approaches can now be complemented by advanced computational analysis allowing the identification of compounds with receptorome, or clinically adverse effect profiles, similar to those of the drug candidate under scrutiny for extending the safety assessment to potential liability targets not captured by classical approaches. Nonclinical data supporting safety can be quite reassuring for drugs with a discovered signal of risk. However, for marketing authorization

  1. 78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

    Science.gov (United States)

    2013-06-10

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

  2. Council for Nuclear Safety annual report 1988/89

    International Nuclear Information System (INIS)

    1989-01-01

    An overview of the structure, duties and activities of the Council for Nuclear Safety during 1988/1989 is presented in this annual report. It is the Council's first duty to ensure that all aspects - siting, design, construction and operation - in all areas of the nuclear industry, from mining of the nuclear ores to the ultimate disposal of nuclear waste, are conducted in such a manner that the potential for harm associated with the radioactive properties of the materials involved is kept under proper control. In order to achieve this the Council is responsible for the establishment and application of safety standards, the issuing of nuclear licenses and the evaluation and inspection of nuclear installations to ensure that the licensees are complying with the conditions laid down in the license and that they are adhering to all the safety criteria established by the Council. Other information contained in this annual report is, inter alia, the financial statements of the Council, the meetings attended by members of the Council and the administrative and management aspects of the Council. 8 figs

  3. Enhancing nuclear safety. Annual report 2015. Financial report 2015

    International Nuclear Information System (INIS)

    Le Guludec, Dominique; Niel, Jean-Christophe; Mouton, Georges-Henri; Repussard, Jacques; Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Bigot, Marie-Pierre; Brisset, Yves; Bruna, Giovanni; Charron, Sylvie; Clavelle, Stephanie; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Laloi, Patrick; Lorthioir, Stephane; Monti, Pascale; Rollinger, Francois; Rouyer, Veronique; Tharaud, Christine; Jaunet, Camille; Pascal-Heuze, Charlotte

    2016-01-01

    After some introductory texts proposed by several IRSN head managers, and a brief presentation of some key data illustrating the activity, the annual report presents the main strategic orientations, notably in the field of knowledge management, and of information and communication. After some images illustrating the past year, activities are presented. They first deal with safety: safety of civil nuclear facilities, from decommissioning old reactors to designing those of the future, reactor ageing, severe accidents, fuel, criticality and neutronics, fire and containment, safety and radiation protection of defence-related facilities and activities, geological disposal of radioactive wastes. They secondly deal with security and non-proliferation (nuclear security, nuclear non-proliferation, chemical weapon ban), thirdly with radiation protection for human and environment health (environment monitoring, radionuclide transfer in the environment, radon and polluted sites, human exposure, radiation protection in the workplace, effects of chronic exposures, protection in health care), and fourthly with emergency and post-accident situations (emergency and post-accident preparedness and response). The next part of the activity report addresses issues related to efficiency: improved economic and financial management, property, computer security, quality and corporate social responsibility, human resources, organisation chart. The financial report proposes a management report, financial statements with an appendix to annual accounts, and an auditor's report

  4. 4th annual Safety Day: full of colour!

    CERN Multimedia

    HSE Unit

    2014-01-01

    On Thursday 10 April, more than 240 people took part in the 4th annual Safety Day, organised on the occasion of the World Day for Safety and Health at Work. The HSE Unit, in partnership with the Fire Brigade (GS/FB) and the TE and BE Departments, organised various stands and activities connected with this year’s theme, chosen by the International Labour Organization: "Safety and health in the use of chemicals at work”.   The stands, set up at lunchtime in all three of CERN’s restaurants as well as in the entrance hall of Building 500, were designed to: Remind visitors of the need to use personal protective equipment appropriate to the chemicals they are using; Make visitors aware of the potential environmental impact of using chemicals; Encourage visitors to always read the labels and safety data sheets of dangerous chemicals and everyday domestic products; Inform visitors that a safety training course called “Chemical Risk Awareness&r...

  5. Safety assessment of indoor live fire range, May 1989

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-05-01

    The following Safety Assessment (SA) pertains to the indoor live fire range (LFR) at EG&G Mound Applied Technology plant. The purpose of the indoor LFR is to conduct training with live ammunition for all designated personnel. The SA examines the risks that are attendant to the operation of an indoor LFR for this purpose.

  6. Price-Anderson Nuclear Safety Enforcement Program. 1996 Annual report

    International Nuclear Information System (INIS)

    1996-01-01

    This first annual report on DOE's Price Anderson Amendments Act enforcement program covers the activities, accomplishments, and planning for calendar year 1996. It also includes the infrastructure development activities of 1995. It encompasses the activities of the headquarters' Office of Enforcement in the Office of Environment, Safety and Health (EH) and Investigation and the coordinators and technical advisors in DOE's Field and Program Offices and other EH Offices. This report includes an overview of the enforcement program; noncompliances, investigations, and enforcement actions; summary of significant enforcement actions; examples where enforcement action was deferred; and changes and improvements to the program

  7. Fusion Safety Program annual report, fiscal year 1985

    International Nuclear Information System (INIS)

    Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

    1987-02-01

    The Fusion Safety Program (FSP) has supported magnetic fusion technology for seven years, and this is the seventh annual report issued by the FSP. Program focus is identification of the magnitude and distribution of radioactive inventories in fusion reactors, and research and analysis of postulated accident scenarios that could cause the release of a portion of these inventories. Research results are used to develop improved designs that can reduce the probability and magnitude of such releases and thus improve the overall safety of fusion reactors. During FY-1985, research activities continued and participation continued on the Ignition Systems Project (ISP). This report presents the significant results of EGandG Idaho, Inc., activities and those from outside contracts, and includes a list of publications produced during the year, and activities planned for FY-1986

  8. 76 FR 37646 - Safety Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, City of...

    Science.gov (United States)

    2011-06-28

    ... Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, City of Sausalito... Guard will enforce the Fourth of July Fireworks, City of Sausalito annual safety zone. This action is... for the annual Fourth of July Fireworks, City of Sausalito, safety zone in 33 CFR 165.1191 on July 4...

  9. 242-A Evaporator crystallizer facility integrated annual safety appraisal

    International Nuclear Information System (INIS)

    1991-01-01

    This report provides the results of the Fiscal Year (FY) 1991 Annual Integrated Safety Appraisal of the 242-A Evaporator Crystallizer Facility in the Hanford 200 East Area. The appraisal was conducted in December 1990 and January 1991, by the Waste Tank Safety Assurance (WTSA) organizations in conjunction with Radiological Engineering, Criticality Safety, Packaging and Shipping Safety, Emergency Preparedness, Environmental Compliance, and Quality Assurance. Reports of these eight organizations are presented as Sections 2 through 7 of this report. The purpose of the appraisal was to verify that the 242-A Evaporator meets US Department of Energy (DOE) and Westinghouse Hanford Company (WHC) requirements and current industry standards of good practice for the areas being appraised. A further purpose was to identify areas in which program effectiveness could be improved. In accordance with the guidance of WHC Management Requirements and Procedures (MRP)5.6, previously identified deficiencies which are being resolved by line management were not repeated as Findings or Observations unless progress or intended disposition was considered to be unsatisfactory

  10. 33 CFR 165.151 - Safety Zones; Long Island Sound annual fireworks displays.

    Science.gov (United States)

    2010-07-01

    ... annual fireworks displays. 165.151 Section 165.151 Navigation and Navigable Waters COAST GUARD... § 165.151 Safety Zones; Long Island Sound annual fireworks displays. (a) Safety Zones. The following...) Indian Harbor Yacht Club Fireworks Safety Zone. All waters of Long Island Sound off Greenwich CT, within...

  11. Regulatory control of nuclear safety in Finland. Annual report 2008

    International Nuclear Information System (INIS)

    Kainulainen, E.

    2009-06-01

    This report covers the regulatory control of nuclear safety in 2008, including the design, construction and operation of nuclear facilities, as well as nuclear waste management and nuclear materials. The control of nuclear facilities and nuclear waste management, as well as nuclear non-proliferation, concern two STUK departments: Nuclear Reactor Regulation and Nuclear Waste and Material Regulation. It constitutes the report on regulatory control in the field of nuclear energy, which the Radiation and Nuclear Safety Authority (STUK) is required to submit to the Ministry of Employment and the Economy pursuant to section 121 of the Finnish Nuclear Energy Decree. The first parts of the report explain the basics of the nuclear safety regulation included as part of STUK's responsibilities, as well as the objectives of the operations, and briefly introduce the objects of regulation. The chapter concerning the development and implementation of legislation and regulations describes changes in nuclear legislation, as well as the progress of STUK's YVL Guide revision. The chapter also includes a summary of the application of the updated YVL Guides to nuclear facilities. The section concerning the regulation of nuclear facilities contains a complete safety assessment of the nuclear facilities currently in operation or under construction. For the nuclear facilities in operation, the section describes plant operation, events during operation, annual maintenance, development of the plants and their safety, and observations made during monitoring. Data and observations gained during regulatory activities are reviewed with a focus on ensuring the safety functions of nuclear facilities and the integrity of structures and components. The report also includes a description of the oversight of the operations and quality management of organisations, oversight of operational experience feedback activities, and the results of these oversight activities. The radiation safety of nuclear

  12. B plant/WESF integrated annual safety appraisal

    International Nuclear Information System (INIS)

    Anderson, J.K.

    1990-12-01

    This report provides the results of the Fiscal Year 1990 Annual Integrated Safety Appraisal of the B Plant and Waste Encapsulation and Storage Facility in the Hanford Site 200 East Area. The appraisal was conducted in August and September 1990, by the Defense Waste Disposal Safety group, in conjunction with Health Physics and Emergency Preparedness. Reports of these three organizations for their areas of responsibility are presented. The purpose of the appraisal was to determine if the areas being appraised meet US Department of Energy (DOE) and Westinghouse Hanford Company (WHC) requirements and current industry standards of good practice. A further purpose was to identify areas in which program effectiveness could be improved. In accordance with the guidance of WHC Management Requirements and Procedures 5.6, previously identified deficiencies which are being resolved by line management were not repeated as Findings or Observations unless progress or intended disposition was considered to be unsatisfactory. The overall assessment is that there are no major safety problems associated with current operations. Programs are in place to provide the necessary safety controls, evaluations, overviews, and support. In most respects these programs are being implemented effectively. However, there are a number of deficiencies in details of program design and implementation. The appraisal identified a total of 23 Findings and 27 Observations of deficiencies. All Observations are Seriousness Category 3. Fifteen Findings were Category 2 and 8 were Category 3. Most of the Category 2 Findings were so categorized on the basis of noncompliance with mandatory DOE Orders or WHC policies and procedures, rather than potential risk to personnel

  13. Safety-oriented LWR research. Annual report 1987

    International Nuclear Information System (INIS)

    1988-06-01

    The annual report 1987 includes the results of out-of-pile bundle experiments for severe fuel damage investigations (CORA), aerosol behaviour under core meltdown accident condition, dynamic behaviour of PWR containments, theoretical and experimental investigations of crack growth under thermal and thermomechanical fatigue loading, the thermal hydraulic code COMMIX-1B, the interfacial exchange processes in two-phase flow (NOVA-Program), the retention of penetrating iodine species, the development of exhaust filters and HEPA filter systems, advanced PWR's (APWR's) and related safety considerations, the HERA test facility and the KRISTA-program, and RELAP5/MOD2 post-test analysis of a forced feed reflood experiment. 20 papers are separately indexed in the database. (DG)

  14. Tonopah Test Range Post-Closure Inspection Annual Report, Tonopah Test Range, Nevada, Calendar Year 2003

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Bechtel Nevada

    2004-04-01

    This post-closure inspection report provides documentation of the semiannual inspection activities, maintenance and repair activities, and conclusions and recommendations for calendar year 2003 for eight corrective action units located on the Tonopah Test Range, Nevada.

  15. 78 FR 38803 - Pipeline Safety: Information Collection Activities, Revisions to Incident and Annual Reports for...

    Science.gov (United States)

    2013-06-27

    ... Reports for Gas Pipeline Operators AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... (OMB) Control No. 2137-0522, titled ``Incident and Annual Reports for Gas Pipeline Operators.'' PHMSA...

  16. Atomic Safety and Licensing Board Panel annual report

    International Nuclear Information System (INIS)

    1991-09-01

    In Fiscal Year 1990, The Atomic Safety and Licensing Board Panel (Panel) handled 40 proceedings involving the construction, operation, and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights, and analyzes how the judges and licensing boards of the Panel addressed the wide-ranging issues raised in these proceedings during the year

  17. Advanced Range Safety System for High Energy Vehicles

    Science.gov (United States)

    Claxton, Jeffrey S.; Linton, Donald F.

    2002-01-01

    The advanced range safety system project is a collaboration between the National Aeronautics and Space Administration and the United States Air Force to develop systems that would reduce costs and schedule for safety approval for new classes of unmanned high-energy vehicles. The mission-planning feature for this system would yield flight profiles that satisfy the mission requirements for the user while providing an increased quality of risk assessment, enhancing public safety. By improving the speed and accuracy of predicting risks to the public, mission planners would be able to expand flight envelopes significantly. Once in place, this system is expected to offer the flexibility of handling real-time risk management for the high-energy capabilities of hypersonic vehicles including autonomous return-from-orbit vehicles and extended flight profiles over land. Users of this system would include mission planners of Space Launch Initiative vehicles, space planes, and other high-energy vehicles. The real-time features of the system could make extended flight of a malfunctioning vehicle possible, in lieu of an immediate terminate decision. With this improved capability, the user would have more time for anomaly resolution and potential recovery of a malfunctioning vehicle.

  18. Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada & Kauai Test Facility, Hawaii.

    Energy Technology Data Exchange (ETDEWEB)

    Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

    2005-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b).

  19. Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii

    International Nuclear Information System (INIS)

    Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

    2005-01-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b)

  20. Status of safety at Areva group facilities. 2006 annual report

    International Nuclear Information System (INIS)

    2006-01-01

    This report presents a snapshot of nuclear safety and radiation protection conditions in the AREVA group's nuclear installations in France and abroad, as well as of radiation protection aspects in service activities, as identified over the course of the annual inspections and analyses program carried out by the General Inspectorate in 2006. This report is presented to the AREVA Supervisory Board, communicated to the labor representation bodies concerned, and made public. In light of the inspections, appraisals and coordination missions it has performed, the General Inspectorate considers that the nuclear safety level of the AREVA group's nuclear installations is satisfactory. It particularly noted positive changes on numerous sites and efforts in the field of continuous improvement that have helped to strengthen nuclear safety. This has been possible through the full involvement of management teams, an improvement effort initiated by upper management, actions to increase personnel awareness of nuclear safety culture, and supervisors' heightened presence around operators. However, the occurrence of certain events in facilities has led us to question the nuclear safety repercussions that the changes to activities or organization on some sites have had. In these times of change, drifts in nuclear safety culture have been identified. The General Inspectorate considers that a preliminary analysis of the human and organizational factors of these changes, sized to match the impact the change has on nuclear safety, should be made to ensure that a guaranteed level of nuclear safety is maintained (allowance for changes to references, availability of the necessary skills, resources of the operating and support structures, etc.). Preparations should also be made to monitor the changes and spot any telltale signs of drift in the application phase. Managers should be extra vigilant and the occurrence of any drift should be systematically dealt with ahead of implementing

  1. 76 FR 44531 - Safety Zone; Fourth Annual Chillounge Night St. Petersburg Fireworks Display, Tampa Bay, St...

    Science.gov (United States)

    2011-07-26

    ...-AA00 Safety Zone; Fourth Annual Chillounge Night St. Petersburg Fireworks Display, Tampa Bay, St... proposes to establish a temporary safety zone on the waters of Tampa Bay in St. Petersburg, Florida during the Fourth Annual Chillounge Night St. Petersburg Fireworks Display on Saturday, November 19, 2011...

  2. 76 FR 68098 - Safety Zone; Fourth Annual Chillounge Night St. Petersburg Fireworks Display, Tampa Bay, St...

    Science.gov (United States)

    2011-11-03

    ...-AA00 Safety Zone; Fourth Annual Chillounge Night St. Petersburg Fireworks Display, Tampa Bay, St... Guard is establishing a temporary safety zone on the waters of Tampa Bay in St. Petersburg, Florida during the Fourth Annual Chillounge Night St. Petersburg Fireworks Display on Saturday, November 19, 2011...

  3. 75 FR 35650 - Safety Zone; Northern California Annual Fireworks Events, Independence Day Fireworks

    Science.gov (United States)

    2010-06-23

    ... Zone; Northern California Annual Fireworks Events, Independence Day Fireworks AGENCY: Coast Guard, DHS... July Fireworks safety zone from 7 a.m. through 10 p.m. on July 3, 2010 in position 39[deg]13'55.37'' N... will enforce the safety zone for the annual Kings Beach 4th of July Fireworks in 33 CFR 165.1191 on...

  4. 33 CFR 165.1191 - Safety zones: Northern California annual fireworks events.

    Science.gov (United States)

    2010-07-01

    ... annual fireworks events. 165.1191 Section 165.1191 Navigation and Navigable Waters COAST GUARD... § 165.1191 Safety zones: Northern California annual fireworks events. (a) General. Safety zones are.... Event Description Fireworks display. Date Last Saturday in May. Location 1,000 feet off Pier 30/32...

  5. 75 FR 35649 - Safety Zone; Northern California Annual Fireworks Events, July 4th Fireworks Display

    Science.gov (United States)

    2010-06-23

    ... Zone; Northern California Annual Fireworks Events, July 4th Fireworks Display AGENCY: Coast Guard, DHS... July Fireworks Display safety zone, from 9 a.m. through 10 p.m. on July 4, 2010 in position 39[deg]10... safety zone for the annual Tahoe City 4th of July Fireworks in 33 CFR 165.1191 on July 4, 2010, from 9 a...

  6. 76 FR 31846 - Safety Zone; 28th Annual Humboldt Bay Festival, Fireworks Display, Eureka, CA

    Science.gov (United States)

    2011-06-02

    ...-AA00 Safety Zone; 28th Annual Humboldt Bay Festival, Fireworks Display, Eureka, CA AGENCY: Coast Guard... support of the 28th Annual Humboldt Bay Festival Fireworks Display on the specified waters off the South... Humboldt Bay Festival Fireworks Display. The fireworks display is for entertainment purposes. This safety...

  7. 76 FR 37649 - Safety Zone; Northern California Annual Fireworks Events, July 4th Fireworks Display

    Science.gov (United States)

    2011-06-28

    ... Zone; Northern California Annual Fireworks Events, July 4th Fireworks Display AGENCY: Coast Guard, DHS... annual July 4th Fireworks Display (Tahoe City 4th of July Fireworks Display). This action is necessary to... INFORMATION: The Coast Guard will enforce the safety zone for the annual Tahoe City 4th of July Fireworks in...

  8. Aerospace Safety Advisory Panel Annual Report for 1999

    Science.gov (United States)

    Blomberg, Richard D.

    2000-01-01

    recommendations in this report do not highlight any major, immediate issues that might compromise the safe pursuit of the various NASA programs. They do, however, cover concerns that the Panel believes should be addressed in the interest of maintaining NASA's excellent safety record.The Panel is pleased to note that remedial efforts for some of the findings raised are underway. Given appropriate funding and cooperative efforts among the Administration, the Congress and the various contractors, the Panel is convinced that safety problems can be avoided or solved resulting in lower risk for NASA's human space and aeronautics programs. Section II of this report contains specific findings and recommendations generated by Panel activities during the calendar year 1999. Section III presents more detailed information in support of these findings and recommendations. A current roster of Panel members, consultants, and staff is included as Appendix A. Appendix B contains NASA's response to the findings and recommendations from the 1998 annual report. It has been augmented this year to include brief explanations of why the Panel classified the NASA response as " open,""continuing," or "closed." Appendix C lists the fact-finding activities of the Panel in 1999.

  9. Environmental and Occupational Safety Division annual progress report for 1984

    International Nuclear Information System (INIS)

    1985-11-01

    Over 950 radiation workers were monitored at ORNL for both internal and external exposure to ionizing radiation and radioactive materials in 1984, and no employee exceeded 50% of the applicable DOE dose limit. No internal exposure exceeded 10% of the maximum permissible organ burden, as determined by in-vivo gamma spectrometry. Dose readings from 5000 TLDs and 136,000 pocket meters were determined, and more than 5800 calibrations were performed on these devices. Approximately 82,000 radioassays were performed; among these were 1500 urinalyses and 3000 radiochemical analyses. Over 3000 calibrations were performed for approximately 2000 portable and fixed survey instruments. Response teams were identified in support of the Radiological Assistance Program (RAP). Documentation, procedures, and equipment for the RAP vehicle were upgraded. A long-range environmental plan was issued early in the year and again in June 1984 to document the scope and justification for each project. The DEM is developing an environmental information system for managing DOE-ORO and ORNL environmental data. Five hundred eighty-four waste disposal requests containing 5769 items were handled by the Hazardous Materials Control Group during 1984. The Office of Operational Safety made significant progress in the completion of Safety Analysis Reports for existing facilities. The Radiation and Safety Surveys Department is becoming increasingly involved in work resulting in facility improvement, repair, or upgrade as well as decontamination and decommissioning of older facilities

  10. Industrial safety and applied health physics. Annual report for 1980

    International Nuclear Information System (INIS)

    1981-11-01

    Information is reported in sections entitled: radiation monitoring; Environmental Management Program; radiation and safety surveys; industrial safety and special projects; Office of Operational Safety; and training, lectures, publications, and professional activities. There were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 35 employees received whole body dose equivalents of 10 mSv (1 rem) or greater. There were no releases of gaseous waste from the Laboratory which were of a level that required an incident report to DOE. There were no releases of liquid radioactive waste from the Laboratory which were of a level that required an incident report to DOE. The quantity of those radionuclides of primary concern in the Clinch River, based on the concentration measured at White Oak Dam and the dilution afforded by the Clinch River, averaged 0.16 percent of the concentration guide. The average background level at the Perimeter Air Monitoring (PAM) stations during 1980 was 9.0 μrad/h (0.090 μGy/h). Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.37 Bq/kg (0.01 pCi/g) to 1.5 Bq/kg (0.04 pCi/g), and the uranium-235 content ranged from 0.7 Bq/kg (0.02 pCi/g) to 16 Bq/kg (0.43 pCi/g). Grass samples were collected at all perimeter and remote monitoring stations and analyzed for twelve radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.04 Bq/kg (0.001 pCi/g) to 0.07 Bq/kg (0.002 pCi/g), and the uranium-235 content ranged from 0.37 Bq/kg (0.01 pCi/g) to 12 Bq/kg

  11. The General Safety Group Annual Report 2001/2002

    CERN Document Server

    Weingarten, W

    2003-01-01

    This report summarizes the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division during 2001 and 2002, and the results obtained. The different topics in which the group is active are covered: general safety inspections and ergonomics, electrical, chemical and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

  12. 75 FR 19304 - Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone

    Science.gov (United States)

    2010-04-14

    ... previously published in Coast Guard regulations. These safety zones are necessary to protect spectators...-AA00 Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone AGENCY: Coast Guard, DHS. ACTION: Notice of proposed rulemaking. SUMMARY: The Coast Guard proposes establishment of safety...

  13. 75 FR 36615 - Pipeline Safety: Information Collection Gas Distribution Annual Report Form

    Science.gov (United States)

    2010-06-28

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 192 [Docket No. PHMSA-RSPA-2004-19854] Pipeline Safety: Information Collection Gas Distribution Annual Report Form AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Request...

  14. Ferrocyanide safety project ferrocyanide aging studies FY 1995 annual report

    International Nuclear Information System (INIS)

    Lilga, M.A.; Alderson, E.V.; Hallen, R.T.

    1995-09-01

    This annual report gives the results of the work conducted by the Pacific Northwest Laboratory in FY 1995 on Task 3 of the Ferrocyanide Safety Project, Ferrocyanide Aging Studies. Aging refers to the dissolution and hydrolysis of simulated Hanford ferrocyanide waste in alkaline aqueous solutions by radiolytic and chemical means. The ferrocyanide simulant primarily used in these studies was dried In-Farm-1B, Rev. 7, prepared by Westinghouse Hanford Company to simulate the waste generated when the In-Farm flowsheet was used to remove radiocesium from waste supernates in single-shell tanks at the Hanford Site. In the In-Farm flowsheet, nickel ion and ferrocyanide anion were added to waste supernates to precipitate sodium nickel ferrocyanide, Na 2 NiFe(CN) 6 , and co-precipitate radiocesium. Once the radiocesium was removed, supernates were pumped from the tanks, and new wastes from cladding removal processes or from evaporators were added. These new wastes were typically highly caustic, having hydroxide ion concentrations of over 1 M and as high as 4 M. The Aging Studies task is investigating reactions this caustic waste may have had with the precipitated ferrocyanide waste in a radiation field. In previous Aging Studies research, Na 2 NiFe(CN) 6 in simulants was shown to dissolve in basic solutions, forming insoluble Ni(OH) 2 and soluble Na 4 Fe(CN) 6 . The influence on solubility of base strength, sodium ion concentration, anions, and temperature was previously investigated. The results may indicate that even ferrocyanide sludge that did not come into direct contact with highly basic wastes may also have aged significantly

  15. Ferrocyanide safety program cyanide speciation studies FY 1993 annual report

    International Nuclear Information System (INIS)

    Bryan, S.A.; Pool, K.H.; Bryan, S.L.; Sell, R.L.; Thomas, L.M.P.

    1993-09-01

    This report summarizes Pacific Northwest Laboratory's (PNL) FY 1993 progress toward developing and implementing methods to identify and quantify cyanide species in ferrocyanide tank waste. Currently, there are 24 high-level waste storage tanks at the US Department of Energy's (DOE) Hanford Site that have been placed on a Ferrocyanide Tank Watchlist because they contain an estimated 1000 g-moles or more of precipitated ferrocyanide. This amount of ferrocyanide is of concern because the consequences of a potential explosion may exceed those reported previously in safety analyses. To bound the safety concern, methods are needed to definitively measure and quantitate the amount of ferrocyanides present within actual waste tanks to a lower limit of at least 0.1 wt % up to approximately 15 wt %. The target analyte concentration for cyanide in waste is approximately 0.1 to 15 wt % (as CN) in the original undiluted sample. After dissolution of the original sample and appropriate dilutions, the concentration range of interest in the analytical solutions can vary between 0.001 to 0.1 wt % (as CN)

  16. Applied Health Physics and Safety annual report for 1975

    International Nuclear Information System (INIS)

    1976-08-01

    This report describes and summarizes the activities of the applied sections and/or groups of the Health Physics Division. Projects and activities covered include personnel monitoring, environmental monitoring, radiation and safety surveys, and industrial safety

  17. Industrial safety and applied health physics. Annual report for 1977

    International Nuclear Information System (INIS)

    Auxier, J.A.; Davis, D.M.

    1978-06-01

    Progress is reported on the following: radiation monitoring with regard to personnel monitoring and health physics instrumentation; environs surveillance with regard to atmospheric monitoring, water monitoring, radiation background measurements, and soil and grass samples; radiation and safety surveys with regard to laboratory operations monitoring, radiation incidents, and laundry monitoring; industrial safety and special projects with regard to accident analysis, disabling injuries, and safety awards

  18. National Institute for Radiological Protection and Nuclear Safety - IRSN. Annual Report 2016, Financial Report 2016

    International Nuclear Information System (INIS)

    2017-01-01

    IRSN is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues in France and in the international arena. Its work therefore concerns a wide range of complementary fields, including environmental monitoring, radiological emergency response, radiation protection and human health in normal and accident situations, prevention of major accidents, and safety and security relating to nuclear reactors, plants, laboratories, transportation, and waste. It also carries out assessments in the nuclear defense field. In addition, IRSN contributes to government policy in nuclear safety, the protection of human health and the environment against ionizing radiation, and measures aimed at safeguarding nuclear materials, facilities and transportation operations against the risk of malicious acts. Within this context, it interacts with all the organizations concerned including public authorities, in particular nuclear safety and security authorities, local authorities, businesses, research organizations, and stakeholder associations. This document is IRSN's annual and financial report for 2016. Content: 1 - Activity Key Figures; 2 - Strategy; 3 - Panorama 2016; 4 - Activities: safety (Safety of civil nuclear facilities, Experimental reactors, Nuclear fuel cycle facilities, Human and organizational factors, Reactor aging, Severe accidents, Fuel, Criticality, Fire and containment, Natural hazards, Defense-related facilities and activities, Radioactive waste management, Geological disposal of radioactive waste); security and nonproliferation (Nuclear security, Nuclear nonproliferation, Chemical weapons ban); radiation protection - human and environment health (Environmental monitoring, Radon and polluted sites, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); emergency and post-accident situations (Emergency preparedness and response, Post

  19. 76 FR 37650 - Safety Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, South Lake...

    Science.gov (United States)

    2011-06-28

    ... Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, South Lake Tahoe Gaming... will enforce the safety zone for the annual Fourth of July Fireworks, South Lake Tahoe Gaming Alliance (Lights on the Lake Fireworks Display). This action is necessary to control vessel traffic and to ensure...

  20. 75 FR 35651 - Safety Zone, Long Island Sound Annual Fireworks Displays

    Science.gov (United States)

    2010-06-23

    ... Zone, Long Island Sound Annual Fireworks Displays AGENCY: Coast Guard, DHS. ACTION: Notice of enforcement of regulation. SUMMARY: The Coast Guard will enforce annual fireworks display safety zones for thirteen fireworks displays taking place throughout the Sector Long Island Sound Captain of the Port Zone...

  1. Fusion safety program annual report fiscal year 1997

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2)

  2. Fusion safety program annual report fiscal year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C. [and others

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2).

  3. Fusion safety program Annual report, Fiscal year 1995

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

    1995-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities

  4. Fusion Safety Program annual report, fiscal year 1994

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1995-03-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1994. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions, including the University of Wisconsin. The technical areas covered in this report include tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate data base development, and thermalhydraulics code development and their application to fusion safety issues. Much of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and of the technical support for commercial fusion facility conceptual design studies. A major activity this year has been work to develop a DOE Technical Standard for the safety of fusion test facilities

  5. Safety Review Committee - Annual Report 1991-1992

    International Nuclear Information System (INIS)

    1993-01-01

    During the year under review. The Safety Review Committee (SRC) assessed the safety of ANSTO's operations. This was done by site visits, examination of documentation and briefing by ANSTO officers responsible for particular operations, and includes HIFAR and Moata reactors, radioisotope production, packing and dispatch, radioactive waste management practices, occupational health and safety activities and ANSTO's arrangements for public health and safety beyond the site. This report describes the activities and findings of the SRC during the year ending 30 June 1992. 8 figs., ills

  6. 78 FR 40000 - Eighth Coast Guard District Annual Safety Zones; Riverfront Independence Festival Fireworks; Ohio...

    Science.gov (United States)

    2013-07-03

    ...-AA00 Eighth Coast Guard District Annual Safety Zones; Riverfront Independence Festival Fireworks; Ohio.... SUMMARY: The Coast Guard will enforce a Safety Zone for the Riverfront Independence Festival Fireworks on... navigable waters during the Riverfront Independence Festival Fireworks. During the enforcement period, in...

  7. 78 FR 24069 - Safety Zone; 12th Annual Saltwater Classic; Port Canaveral Harbor; Port Canaveral, FL

    Science.gov (United States)

    2013-04-24

    ... under Executive Order 13045, Protection of Children from Environmental Health Risks and Safety Risks. This rule is not an economically significant rule and does not create an environmental risk to health...-AA00 Safety Zone; 12th Annual Saltwater Classic; Port Canaveral Harbor; Port Canaveral, FL AGENCY...

  8. 77 FR 30245 - Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone

    Science.gov (United States)

    2012-05-22

    ...'' N, 082-51'-18.70'' W (NAD 83). This proposed zone would be enforced one evening during the last week...-AA00 Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone AGENCY: Coast Guard... by adding three permanent safety zones within the Captain of the Port Detroit Zone. This action is...

  9. 76 FR 34867 - Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone

    Science.gov (United States)

    2011-06-15

    ....941(a)(51) Target Fireworks, Detroit, MI The first safety zone will be enforced from 7 a.m. on June 24... Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone AGENCY: Coast Guard, DHS. ACTION: Notice of enforcement of regulation. SUMMARY: The Coast Guard will enforce various safety zones for...

  10. 75 FR 41762 - Safety Zone; Annual Kennewick, WA, Columbia Unlimited Hydroplane Races, Kennewick, WA

    Science.gov (United States)

    2010-07-19

    ...-AA00 Safety Zone; Annual Kennewick, WA, Columbia Unlimited Hydroplane Races, Kennewick, WA AGENCY..., Columbia Unlimited Hydroplane Races'' also known as the Tri-City Water Follies Hydroplane Races. The safety... power and responsibilities between the Federal Government and Indian tribes. Energy Effects We have...

  11. Environmental and Occupational Safety Division annual progress report for 1983

    International Nuclear Information System (INIS)

    1984-11-01

    This report presents summaries of activities conducted during 1983 in the following areas: radiation monitoring; health physics instrumentation development; environmental management; atmospheric monitoring; water monitoring; background radiation measurements; soil and grass samples; deer samples; calculation of potential radiation dose to the public; industrial safety; and operational safety

  12. Fusion Safety Program Annual Report, Fiscal Year 1996

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1996-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1996. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. The objective is to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, chemical reactions and activation product release, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Work done for ITER this year has focused on developing the needed information for the Non- Site- Specific Safety Report (NSSR-1). A final area of activity described is development of the new DOE Technical Standards for Safety of Magnetic Fusion Facilities

  13. Health, Safety, and Environment Division: Annual progress report 1987

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.A. (comp.)

    1988-04-01

    The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems arise occasionally from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed to study specific problems for the Department of Energy and to help develop better occupational health and safety practices.

  14. Health, Safety, and Environment Division: Annual progress report 1987

    International Nuclear Information System (INIS)

    Rosenthal, M.A.

    1988-04-01

    The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems arise occasionally from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed to study specific problems for the Department of Energy and to help develop better occupational health and safety practices

  15. Health, Safety, and Environment Division annual report, 1988

    International Nuclear Information System (INIS)

    Rosenthal, M.A.

    1989-10-01

    The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environmental protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems occasionally arise from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed, to study specific problems for the Department of Energy and to help develop better occupational health and safety practices. 52 refs

  16. Fusion Safety Program annual report: Fiscal year 1986

    International Nuclear Information System (INIS)

    Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

    1987-06-01

    This report summarizes the Fusion Safety Program's (FSP) major activities in fiscal year 1986. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and EG and G Idaho, Inc., is the prime contractor for FSP, which was initiated in 1979. Activities are conducted at the INEL and in participating facilities, including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in this report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruption, risk assessment methodology, and computer code development for reactor transients. Contributions to the Technical Planning Activity (TPA) and the ''white paper'' study by the Environmental, Safety,and Economics Committee (ESECOM) are summarized. The report also includes a summary of the safety and environmental analysis and documentation performed by the INEL for the Compact Ignition Tokamak (CIT) design project

  17. Fusion Safety Program annual report, Fiscal Year 1993

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1993-12-01

    This report summarizes the major activities of the Fusion Safety Program in Fiscal Year 1993. The Idaho National Engineering Laboratory (INEL) has been designated by DOE as the lead laboratory for fusion safety, and EG ampersand G Idaho, Inc., is the prime contractor for INEL operations. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations, including universities and private companies. Technical areas covered in the report include tritium safety, beryllium safety, activation product release, reactions involving potential plasma-facing materials, safety of fusion magnet systems, plasma disruptions and edge physics modeling, risk assessment failure rates, computer codes for reactor transient analysis, and regulatory support. These areas include work completed in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed at the INEL for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor projects at the Princeton Plasma Physics Laboratory and a summary of the technical support for the ARIES/PULSAR commercial reactor design studies

  18. 76 FR 77125 - Safety Zone; Sausalito Yacht Club's Annual Lighted Boat Parade and Fireworks Display, Sausalito, CA

    Science.gov (United States)

    2011-12-12

    ...-AA00 Safety Zone; Sausalito Yacht Club's Annual Lighted Boat Parade and Fireworks Display, Sausalito... of the Sausalito Yacht Club's Annual Lighted Boat Parade and Fireworks Display. This temporary safety...-Waterfront Foundation will sponsor the Sausalito Yacht Club's Annual Lighted Boat Parade and Fireworks...

  19. 33 CFR 165.1332 - Safety Zones; annual firework displays within the Captain of the Port, Puget Sound Area of...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety Zones; annual firework... Limited Access Areas Thirteenth Coast Guard District § 165.1332 Safety Zones; annual firework displays... from the following launch sites: Captain of the Port Puget Sound AOR Annual Firework Displays Event...

  20. 76 FR 37646 - Safety Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, Lake Tahoe, CA

    Science.gov (United States)

    2011-06-28

    ... Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, Lake Tahoe, CA AGENCY... annual safety zone for the Fourth of July Fireworks, Lake Tahoe, California, located off Incline Village...,000 foot safety zone for the annual Fourth of July Fireworks Display in 33 CFR 165.1191 on July 4...

  1. Nuclear and radiation safety in Slovenia. Annual report 1997

    International Nuclear Information System (INIS)

    1998-01-01

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 1997. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. Contributions to the report were furthermore prepared by competent authorities in the field of nuclear safety: the Agency for Radwaste Management (ARAO), the Milan Copic Nuclear Training Centre, etc. The report contains 17 chapters. (author)

  2. Population genetics and the evolution of geographic range limits in an annual plant.

    Science.gov (United States)

    Moeller, David A; Geber, Monica A; Tiffin, Peter

    2011-10-01

    Abstract Theoretical models of species' geographic range limits have identified both demographic and evolutionary mechanisms that prevent range expansion. Stable range limits have been paradoxical for evolutionary biologists because they represent locations where populations chronically fail to respond to selection. Distinguishing among the proposed causes of species' range limits requires insight into both current and historical population dynamics. The tools of molecular population genetics provide a window into the stability of range limits, historical demography, and rates of gene flow. Here we evaluate alternative range limit models using a multilocus data set based on DNA sequences and microsatellites along with field demographic data from the annual plant Clarkia xantiana ssp. xantiana. Our data suggest that central and peripheral populations have very large historical and current effective population sizes and that there is little evidence for population size changes or bottlenecks associated with colonization in peripheral populations. Whereas range limit populations appear to have been stable, central populations exhibit a signature of population expansion and have contributed asymmetrically to the genetic diversity of peripheral populations via migration. Overall, our results discount strictly demographic models of range limits and more strongly support evolutionary genetic models of range limits, where adaptation is prevented by a lack of genetic variation or maladaptive gene flow.

  3. Annual plan of research on safety techniques against low level radioactive wastes, FY1994-FY1999

    International Nuclear Information System (INIS)

    1994-01-01

    The safety research on the disposal of low level radioactive waste has been promoted based on the annual plan decided by the committee on radiative waste safety regulation of the Nuclear Safety Commission. Hereafter, the disposal of low level radioactive waste in ocean is never selected. As to the subjects of the safety research which should be carried out for five years from 1994, the necessity, the contents of research, the organs that carry out the research and so on were deliberated, and the results are made into the annual plan, therefore, it is reported. The way of thinking on the safety research, the contents for which efforts should be exerted as the safety research, and the matters to which attention should be paid are shown. As for the annual plan of safety research, the necessity and the outline of the safety research on the disposal in strata, the concrete subjects and their contents, and the necessity and the outline of the safety research on the reuse, the concrete subjects and their contents are reported. The radioactive waste is those produced by the operation of nuclear reactor facilities, those containing TRU nuclides and RI waste. (K.I.)

  4. Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

    International Nuclear Information System (INIS)

    Koelzer, W.

    1993-05-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  5. Annual report 1991 of the Central Safety Department

    International Nuclear Information System (INIS)

    Koelzer, W.

    1992-04-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  6. Annual report 1988 of the Central Safety Department

    International Nuclear Information System (INIS)

    Koelzer, W.; Urban, M.

    1989-04-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1988 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

  7. Annual technical progress report: reactor safety, Government fiscal year 1978

    International Nuclear Information System (INIS)

    1978-01-01

    Progress in LMFBR safety studies on accident debris behavior is reported under the following subtask titles: high-temperature-concentration aerosols, large-scale molten fuel tests, sodium release tests, and risk analysis

  8. Reactor safety. Annual technical progress report, Government fiscal year 1979

    International Nuclear Information System (INIS)

    1980-01-01

    Information is presented on LMFBR reactor safety concerning the energetics effects of sodium spray fires; sodium drop and spray burning; core debris accommodation; attenuation in containment; and attenuation in the environment

  9. Annual report 1990 of the Central Safety Department

    International Nuclear Information System (INIS)

    Koelzer, W.; Urban, M.

    1991-04-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  10. Applied health physics and safety annual report for 1976

    International Nuclear Information System (INIS)

    Auxier, J.A.; Davis, D.M.

    1977-08-01

    Progress is reported in the following areas of research: personnel monitoring; health physics instrumentation; atmospheric monitoring; water monitoring; radiation background measurements; soil samples; laboratory operations monitoring; radiation incidents; laundry monitoring; accident analysis; and industrial safety

  11. Rossendorf Research Center, Institute of Safety Research. Annual report 1991

    International Nuclear Information System (INIS)

    Boehmert, J.; Weiss, F.P.

    1992-08-01

    The working program covers above all topics concerning the assessment of design basis safety and the increase of operational safety of the WWER type reactors. The topics are directed to the WWER-440/213 type and to the WWER-1000 type, and are dealt with by the three departments, i.e. incident analysis, neutron embrittlement, and mechanical integrity. One paper is concerned with the determination of the neutron field of HERA. (orig.) [de

  12. 1980 Annual status report: safety of nuclear materials

    International Nuclear Information System (INIS)

    1981-01-01

    The programme Safety of Nuclear Materials is essentially dealing with long-term safety aspects of the radioactive waste management. The long-term risk of the radioactive waste is due to the presence of alpha-emitting actinides (plutonium, americium, neptunium) and of some long-lived fission products. Evaluation of long-term risk of radioactive waste disposal; assessment studies on alpha-waste management; non-destructive assay of plutonium

  13. Annual health, safety and environmental performance report for 1992

    International Nuclear Information System (INIS)

    Orman, R.F.; Richards, S.

    1993-12-01

    This report summarizes the safety and environmental record of the operations of Atomic Energy of Canada Limited (AECL) during 1992. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices

  14. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1999

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    2000-02-01

    The work of the institute is directed to the assessment and enhancement of the safety of large technical plants and to the increase of the effectiveness and environmental sustainability of those facilities. Subjects of investigations are equally nuclear plants and installations of process industries. To achieve the above mentioned goals, the institute is engaged in two scientific fields, i.e. thermo-fluiddynamics including magneto-hydrodynamics (MHD) and materials/components safety. (orig.)

  15. Nuclear and radiological safety in Slovenia in 1998, Annual report

    International Nuclear Information System (INIS)

    Lovincic, D.

    1999-09-01

    The Slovenian Nuclear Safety Administration (SNSA), in cooperation with Health Inspectorate of the Republic of Slovenia and the Administration for Civil Protection and Disaster Relief, has prepared a Report of Nuclear and Radiological Safety in the Republic of Slovenia for 1998. The report presents activities of the SNSA, operation of nuclear facilities, activities of the Agency of Radwaste Management, work of international missions, emergency plan, authorized organizations, monitoring of radioactivity, control of ionizing radiation and nuclear electricity generation

  16. Nuclear and Radiological Safety in Slovenia. Annual Report 1996

    International Nuclear Information System (INIS)

    Lovincic, D.

    1997-08-01

    The Slovenian Nuclear Safety Administration (SNSA), in cooperation with Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1996. The report presents activities of the SNSA; operation of nuclear facilities; activities of the Agency for Radwaste Management; work of international missions; emergency plan; authorized organizations; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation

  17. Nuclear and radiation safety in Slovenia. Annual report 2000

    International Nuclear Information System (INIS)

    Lovincic, D.

    2001-09-01

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 2000. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. (author)

  18. Annual health, safety and environmental performance report for 1992

    International Nuclear Information System (INIS)

    Orman, R.F.; Richards, S.

    1993-12-01

    This report summarizes the safety and environmental record of the operations of Atomic Energy of Canada Limited (AECL) during 1992. an introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices

  19. Fusion Safety Program annual report, fiscal year 1992

    International Nuclear Information System (INIS)

    Holland, D.F.; Cadwallader, L.C.; Herring, J.S.; Longhurst, G.R.; McCarthy, K.A.; Merrill, B.J.; Piet, S.J.

    1993-01-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1992. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG ampersand G Idaho, Inc. is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations including the Westinghouse Hanford Company at the Hanford Engineering Development Laboratory, the Massachusetts Institute of Technology, and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving beryllium, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment failure rate data base, and computer code development for reactor transients. Also included in the report is a summary of the safety and environmental studies performed by the INEL for the Tokamak Physics Experiments and the Tokamak Fusion Test Reactor, the safety analysis for the International Thermonuclear Experimental Reactor design, and the technical support for the ARIES commercial reactor design study

  20. Annual report 1982 of the Central Safety Department

    International Nuclear Information System (INIS)

    Kiefer, H.; Koelzer, W.; Koenig, L.A.

    1983-04-01

    The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project. The centers of interest of r + d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1982 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  1. Fusion Safety Program annual report: Fiscal year 1987

    International Nuclear Information System (INIS)

    Holland, D.F.; Herring, J.S.; Longhurst, G.R.; Lyon, R.E.; Merrill, B.J.; Piet, S.J.

    1988-02-01

    This report summarizes the Fusion Safety Program major activities in fiscal year 1987. The Idaho National Engineering Laboratory (INEL) is the designated lead laboraotry and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. Activities are conducted at the INEL and in participating laboratories including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment methodology, computer codes development for reactor transients, and fusion waste management. Also included in the report is a summary of the safety and environmental analysis and conventional facilities design performed by INEL for the Compact Ignition Tokamak design project, the safety analysis and documentation performed for the Tokamak Ignition/Burn Experimental Reactor design, and the technical support provided to the Environmental Safety and Economics Committee (ESECOM). 42 refs., 17 figs., 4 tabs

  2. 33 CFR 165.161 - Safety zones: Coast Guard Captain of the Port New York annual fireworks displays.

    Science.gov (United States)

    2010-07-01

    ... of the Port New York annual fireworks displays. 165.161 Section 165.161 Navigation and Navigable... Coast Guard District § 165.161 Safety zones: Coast Guard Captain of the Port New York annual fireworks displays. (a) Safety zones. The following areas are designated safety zones: (1) Bar Beach fireworks...

  3. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

  4. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

    International Nuclear Information System (INIS)

    2004-01-01

    The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

  5. 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

  6. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2004

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    2005-01-01

    The Institute of Safety Research (ISR) is one of the six Research Institutes of Forschungszentrum Rossendorf e.V. (FZR e.V.) which is a member institution of the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz (Leibniz Association). Together with the Institute of Radiochemistry, ISR constitutes the research programme ''Safety and Environment'' which is one from three scientific programmes of FZR. In the framework of this research programme, the institute is responsible for the two subprogrammes ''Plant and Reactor Safety'' and ''Thermal Fluid Dynamics'', respectively. We also provide minor contributions to the sub-programme ''Radio-Ecology''. Moreover, with the development of a pulsed photo-neutron source at the radiation source ELBE (Electron linear accelerator for beams of high brilliance and low emittance), we are involved in a networking project carried out by the FZR Institute of Nuclear and Hadron Physics, the Physics Department of TU Dresden, and ISR. (orig.)

  7. Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 1994

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1995-06-01

    Striving for the assessment and enhancement of design based safety, for improving operational safety, and for risk management IFS is engaged in the following methodical fields: - Experimental and theoretical thermo-fluiddynamics, - 3-dimensional neutron kinetics, - characterization of the mechanical behaviour of aged materials and microstructural analysis, -transport calculations of particle and radiation fields, - early failure diagnostics of processes and plants, - hazard ranking of non-nuclear waste deposits and support of the selection of appropriate remediation procedures by means of decision analysis. In 1994, special efforts were directed to the extension of experimental facilities needed for radioactive materials testing and for two phase flow investigations. Moreover, first research projects on the safety of VVER reactors could successfully be finished. (orig./HP)

  8. Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

    International Nuclear Information System (INIS)

    Koelzer, W.

    1994-04-01

    The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

  9. NESHAP Annual Report for CY 2015 Sandia National Laboratories Tonopah Test Range

    Energy Technology Data Exchange (ETDEWEB)

    Evelo, Stacie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-05-01

    This National Emission Standards for Hazardous Air Pollutants (NESHAP) Annual Report has been prepared in a format to comply with the reporting requirements of 40 CFR 61.94 and the April 5, 1995 Memorandum of Agreement (MOA) between the Department of Energy (DOE) and the Environmental Protection Agency (EPA). According to the EPA approved NESHAP Monitoring Plan for the Tonopah Test Range (TTR), 40 CFR 61, subpart H, and the MOA, no additional monitoring or measurements are required at TTR in order to demonstrate compliance with the NESHAP regulation.

  10. Annual health, safety and environmental performance report for 1993

    Energy Technology Data Exchange (ETDEWEB)

    Gallapher, J D; Wright, M G

    1994-05-01

    This report summarizes the occupational health and safety and the environmental protection record of the operations of Atomic Energy of Canada Limited (AECL) during 1993. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes, and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices. (author). 14 figs.

  11. Regulatory oversight of nuclear safety in Finland. Annual report 2011

    Energy Technology Data Exchange (ETDEWEB)

    Kainulainen, E. (ed.)

    2012-07-01

    The report constitutes the report on regulatory control in the field of nuclear energy which the Radiation and Nuclear Safety Authority (STUK) is required to submit once a year to the Ministry of Employment and the Economy pursuant to Section 121 of the Nuclear Energy Decree. The report is also delivered to the Ministry of Environment, the Finnish Environment Institute, and the regional environmental authorities of the localities in which a nuclear facility is located. The regulatory control of nuclear safety in 2011 included the design, construction and operation of nuclear facilities, as well as nuclear waste management and nuclear materials. The first parts of the report explain the basics of nuclear safety regulation included as part of STUK's responsibilities, as well as the objectives of the operations, and briefly introduce the objects of regulation. The chapter concerning the development and implementation of legislation and regulations describes changes in nuclear legislation, as well as the progress of STUK's YVL Guide revision work. The section concerning the regulation of nuclear facilities contains an overall safety assessment of the nuclear facilities currently in operation or under construction. The chapter concerning the regulation of the final disposal project for spent nuclear fuel de-scribes the preparations for the final disposal project and the related regulatory activities. The section concerning nuclear non-proliferation describes the nuclear non-proliferation control for Finnish nuclear facilities and final disposal of spent nuclear fuel, as well as measures required by the Additional Protocol of the Safeguards Agreement. The chapter describing the oversight of security arrangements in the use of nuclear energy discusses oversight of the security arrangements in nuclear power plants and other plants, institutions and functions included within the scope of STUK's regulatory oversight. The chapter also discusses the national and

  12. Annual health, safety and environmental performance report for 1993

    International Nuclear Information System (INIS)

    Gallapher, J.D.; Wright, M.G.

    1994-05-01

    This report summarizes the occupational health and safety and the environmental protection record of the operations of Atomic Energy of Canada Limited (AECL) during 1993. An introduction highlights the results and describes the facilities and organizational systems. Subsequent sections indicate the performance of the company with respect to personnel radiation exposures, occupational injuries, the handling of wastes, and the release of materials into the environment. Programs in health, safety and environmental protection are presented, along with site remediation and emergency preparedness practices. (author). 14 figs

  13. Nuclear Safety Research and Facilities Department. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  14. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

    2000-01-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

  15. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

  16. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

  17. Nuclear Safety Research and Facilities Department. Annual report 1999

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  18. Nuclear Safety Research and Facilities department annual report 1996

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Heydorn, K.; Oelgaard, P.L.

    1997-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1996. The Department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 2 tabs., 28 ills

  19. Nuclear Safety Research and Facilities Department annual report 1997

    International Nuclear Information System (INIS)

    Majborn, B.; Aarkrog, A.; Brodersen, K.

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  20. Nuclear Safety Research and Facilities Department annual report 1998

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  1. Nuclear Safety Research Department annual progress report 1993

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hoejerup, C.F.

    1994-02-01

    The report describes the work of the Nuclear Safety Research Department during 1993. The activities cover health physics, reactor physics, operation of the small reactor DR1, and radioactive waste management. Lists of staff and publications are included together with a summary of the staff's participation in international committees. (au) (2 tabs., 12 ills.)

  2. Nuclear Safety Research Department annual progress report 1994

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hoejerup, C.F.

    1995-03-01

    The report describes the work of the Nuclear Safety Research Department during 1994. The activities cover health physics, reactor physics, operation of the small reactor DR1, and radioactive waste management. Lists of staff and publications are included together with a summary of the staff's participation in international committees. (au) (1 tab., 12 ills.)

  3. Nuclear Safety Research Department annual progress report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B; Brodersen, K; Damkjaer, A; Hoejerup, C F [eds.

    1995-03-01

    The report describes the work of the Nuclear Safety Research Department during 1994. The activities cover health physics, reactor physics, operation of the small reactor DR1, and radioactive waste management. Lists of staff and publications are included together with a summary of the staff`s participation in international committees. (au) (1 tab., 12 ills.).

  4. Nuclear Safety Research Department. Annual progress report 1991

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Hoejerup, C.F.; Heikel Vinther, F.

    1992-03-01

    The report describes the work of the Nuclear Safety Research Department during 1991. The activities cover health physics, reactor physics, operation of the educational reactor DR 1, and waste management. Lists of staff and publications are included together with a summary of participation in international working groups etc. (au) (5 ills., 59 refs.)

  5. Nuclear Safety Research Department annual progress report 1992

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Hoejerup, C.F.; Heikel Vinther, F.

    1993-03-01

    The report describes the work of the Nuclear Safety Research Department during 1992. The activities cover health physics, reactor physics, operation of the Danish educational reactor DR1, and waste management. Lists of staff and publications are included together with a summary of the staff's participation in international committees. (au)

  6. Nuclear Safety Research Department. Annual progress report 1990

    International Nuclear Information System (INIS)

    Heikel Vinther, F.

    1991-07-01

    The report describes the work of the Nuclear Safety Research Department during 1990. The activities cover health physics, reactor physics, operation of the educational reactor DR 1, and waste management. Lists of staff and publications are included together with a summary of participation in international working groups etc. (au) 3 ills., 30 refs

  7. Nuclear Safety Bureau. Annual Report 1996-1997

    International Nuclear Information System (INIS)

    1997-01-01

    Throughout the year the Nuclear Safety Bureau (NSB) continued its regulatory approach to monitor and review the safety of nuclear plant operated by the Australian Nuclear Science and Technology Organisation (ANSTO). This included an ongoing regime of safety audits against the authorised arrangements in ANSTO's safety documentation and the bureau's expectations for nuclear plant drawn from international best practice. The NSB invited the participation of officers of the Australian Radiation Laboratory in these audits. Aspects of ANSTO's operation of nuclear plant reviewed by the NSB included training and accreditation of operations staff, abnormal occurrences, modifications to plant and emergency arrangements and exercises for the Lucas Heights Science and Technology Centre. Audits of HIFAR were also conducted on operating logs, radiation protection and radioactive discharges. Based on the reviews and audits conducted by the NSB, and ANSTO's actions in responding to the bureau's requests and requirements for actions, the NSB concluded that ANSTO's nuclear plant operated safely throughout the year, and that risks to on-site personnel and the public were maintained at acceptably low levels

  8. Regulatory control of nuclear safety in Finland. Annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K. [ed.

    1999-10-01

    The report describes regulatory control of the safe use of nuclear energy by the Radiation and Nuclear Safety Authority (STUK) in 1998. STUK is the Finnish nuclear safety authority. The submission of this report to the Ministry of Trade and Industry is stipulated in Section 121 of the Nuclear Energy Decree. It was verified by regulatory control that the operation of Finnish NPPs was in compliance with conditions set out in the operating licences of the plants and with regulations currently in force. In addition to supervising the normal operation of the plants, STUK oversaw projects carried out at the plant units, which related to the uprating of their power and the improvement of their safety. STUK issued to the Ministry of Trade and Industry a statement about applications for the renewal of the operating licences of Loviisa and Olkiluoto NPPs, which had been submitted by Imatran Voima Oy and Teollisuuden Voima Oy. Regulatory activities in the field of nuclear waste management were focused on the storage and final disposal of spent fuel as well as the treatment, storage and final disposal of reactor waste. STUK issued a statement to the Ministry of Trade and Industry about an environmental impact assessment programme pertaining to a spent fuel repository project, which had been submitted by Posiva Oy, as well as on Imatran Voima Oy's application concerning the operation of a repository for medium- and low-level reactor waste from Loviisa NPP. The use of nuclear materials was in compliance with the regulations currently in force and also the whereabouts of every batch of nuclear material were ensured by safeguards control. In international safeguards, important changes took place, which were reflected also in safeguards activities at national level. International co-operation continued based on financing both from STUK's budget and from additional sources. The focus of co-operation funded from outside sources was as follows: improvement of the safety of

  9. Regulatory control of nuclear safety in Finland. Annual report 1998

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1999-10-01

    The report describes regulatory control of the safe use of nuclear energy by the Radiation and Nuclear Safety Authority (STUK) in 1998. STUK is the Finnish nuclear safety authority. The submission of this report to the Ministry of Trade and Industry is stipulated in Section 121 of the Nuclear Energy Decree. It was verified by regulatory control that the operation of Finnish NPPs was in compliance with conditions set out in the operating licences of the plants and with regulations currently in force. In addition to supervising the normal operation of the plants, STUK oversaw projects carried out at the plant units, which related to the uprating of their power and the improvement of their safety. STUK issued to the Ministry of Trade and Industry a statement about applications for the renewal of the operating licences of Loviisa and Olkiluoto NPPs, which had been submitted by Imatran Voima Oy and Teollisuuden Voima Oy. Regulatory activities in the field of nuclear waste management were focused on the storage and final disposal of spent fuel as well as the treatment, storage and final disposal of reactor waste. STUK issued a statement to the Ministry of Trade and Industry about an environmental impact assessment programme pertaining to a spent fuel repository project, which had been submitted by Posiva Oy, as well as on Imatran Voima Oy's application concerning the operation of a repository for medium- and low-level reactor waste from Loviisa NPP. The use of nuclear materials was in compliance with the regulations currently in force and also the whereabouts of every batch of nuclear material were ensured by safeguards control. In international safeguards, important changes took place, which were reflected also in safeguards activities at national level. International co-operation continued based on financing both from STUK's budget and from additional sources. The focus of co-operation funded from outside sources was as follows: improvement of the safety of Kola and

  10. Oak Ridge National Laboratory Health and Safety Long-Range Plan: Fiscal years 1989--1995

    Energy Technology Data Exchange (ETDEWEB)

    1989-06-01

    The health and safety of its personnel is the first concern of ORNL and its management. The ORNL Health and Safety Program has the responsibility for ensuring the health and safety of all individuals assigned to ORNL activities. This document outlines the principal aspects of the ORNL Health and Safety Long-Range Plan and provides a framework for management use in the future development of the health and safety program. Each section of this document is dedicated to one of the health and safety functions (i.e., health physics, industrial hygiene, occupational medicine, industrial safety, nuclear criticality safety, nuclear facility safety, transportation safety, fire protection, and emergency preparedness). Each section includes functional mission and objectives, program requirements and status, a summary of program needs, and program data and funding summary. Highlights of FY 1988 are included.

  11. Oak Ridge National Laboratory Health and Safety Long-Range Plan: Fiscal years 1989--1995

    International Nuclear Information System (INIS)

    1989-06-01

    The health and safety of its personnel is the first concern of ORNL and its management. The ORNL Health and Safety Program has the responsibility for ensuring the health and safety of all individuals assigned to ORNL activities. This document outlines the principal aspects of the ORNL Health and Safety Long-Range Plan and provides a framework for management use in the future development of the health and safety program. Each section of this document is dedicated to one of the health and safety functions (i.e., health physics, industrial hygiene, occupational medicine, industrial safety, nuclear criticality safety, nuclear facility safety, transportation safety, fire protection, and emergency preparedness). Each section includes functional mission and objectives, program requirements and status, a summary of program needs, and program data and funding summary. Highlights of FY 1988 are included

  12. Regulatory control of nuclear safety in Finland. Annual report 1997

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1998-08-01

    The report describes regulatory control of the use of nuclear energy by the Radiation and Nuclear Safety Authority (STUK) in Finland in 1997. Nuclear regulatory control ascertained that the operation of Finnish NPPs was in compliance with the conditions set out in operating licences and current regulations. In addition to NPP normal operation, STUK oversaw projects at the plant units relating to power uprating and safety improvements. STUK prepared statements for the Ministry of Trade and Industry about the applications for renewing the operating licenses of Loviisa and Olkiluoto NPPs. The most important items of supervision in nuclear waste management were studies relating to the final disposal of spent fuel from NPPs and the review of the licence application for a repository for low- and intermediate-level reactor waste from Loviisa NPP. Preparation of general safety regulations for the final disposal of spent nuclear fuel, to be published in the form of a Council of State Decision, was started. By safeguards control, the use of nuclear materials was verified to be in compliance with current regulations and that the whereabouts of every batch of nuclear material were always known. Nuclear material safeguards were stepped up to prevent illicit trafficking of nuclear materials and other radioactive materials. In co-operation with the Ministry for Foreign Affairs and the Institute of Seismology (University of Helsinki), preparations were undertaken to implement the Comprehensive Nuclear Test Ban Treaty (CTBT). For enforcement of the Treaty and as part of the international regulatory approach, STUK is currently developing laboratory analyses relating to airborne radioactivity measurements. The focus of co-operation funded by external sources was as follows: improvement of the safety of Kola and Leningrad NPPs, improvement of nuclear waste management in North-West Russia, development of the organizations of nuclear safety authorities in Eastern Europe and development

  13. Research work for improving LWR safety. 1991 annual report

    International Nuclear Information System (INIS)

    1992-08-01

    The work performed in 1991 for the PNS project centers on various phenomena of severe fuel damage and on selected aspects of a core meltdown accident, relating to aerosol behaviour and filter engineering, and to methods of assessing and minimizing the radiological impacts of a reactor accident. One paper included in this annual report summarizes the evaluation of experiments carried out in 1990 at the Wuerenlingen PROTEUS reactor. The 1991 task programme of the project for the first time included research into extreme load conditions affecting the containment in a core meltdown accident; first results are given of the experiments performed. (orig./DG) [de

  14. Fusion Reactor Safety Research program. Annual report, FY-80

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1981-06-01

    The report is in three sections. Outside contracts includes a report of newly-started study at the General Atomic Company to consider safety implications of low-activation materials, portions of two papers from ongoing work at PNL and ANL, reports of the lithium spill work at HEDL, the LITFIRE code development at MIT, and risk assessment at MIT, all of which are an expansion of FY-79 outside contracts. EG and G Activities includes adaptations of four papers of ongoing work in transient code development, tritium system risk assessment, heat transfer and fluid flow analysis, and fusion safety data base. Program Plan Development includes the Executive Summary of the Plan, which was completed in FY-80, and is accompanied by a list of publications and a brief outline of proposed FY-81 activities to be based on the Program Plan

  15. Forschungszentrum Rossendorf. Institute of Safety Research. Annual report 1998

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1999-07-01

    The Institute of Safety Research is one of the five scientific institutes of Forschungszentrum Rossendorf e.V. The Forschungszentrum Rossendorf is a member of the 'Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz' und is funded by the Federal Ministry of Education and Research and by the Saxon Ministry of Science and Arts with 50% each. The research work of the institute aims at the assessment and increase of the safety and environmental sustainability of technical plants. The emphasis is put on the development and validation of mathematical and physical models for process and plant analysis, and of techniques for process and components monitoring. Subject of investigations are equally nuclear plants and installations of process industries. (orig.)

  16. Nuclear and radiation safety in Slovenia. Annual report 2001

    International Nuclear Information System (INIS)

    Janzekovic, H.

    2002-01-01

    The Slovenian Nuclear Safety Administration (SNSA) has prepared a Report on Nuclear and Radiation Safety in Slovenia for 2001 as a regular form of reporting to the citizens of the Republic of Slovenia on the activities related to the nuclear fuel cycle and the use of the ionising sources. The report has been prepared in collaboration with the Health Inspectorate of the Republic of Slovenia (HIRS), the Administration for Civil Protection and Disaster Relief (ACPDR), the Pool for Assurance and Reinsurance of Liability for Nuclear Damage and the Pool for Decommissioning of the NPP Krsko and for the Radwaste Disposal from the NPP Krsko. The reports of the Agency for Radioactive Waste Management (ARAO), the Institute of Oncology, the Department of Nuclear Medicine of the Medical Centre Ljubljana and the technical support organisations are also included. The SNSA made no crucial modifications to the reports of the above mentioned institutions. The modifications were made just facilitate a reading of the reports. (author)

  17. Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report

    International Nuclear Information System (INIS)

    1998-01-01

    This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV's) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG ampersand G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin). Sandia / Sandia Corporation (Lockheed-Martin)

  18. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2004

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F.P.; Rindelhardt, U. (eds.)

    2005-07-01

    The Institute of Safety Research (ISR) is one of the six Research Institutes of Forschungszentrum Rossendorf e.V. (FZR e.V.) which is a member institution of the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz (Leibniz Association). Together with the Institute of Radiochemistry, ISR constitutes the research programme ''Safety and Environment'' which is one from three scientific programmes of FZR. In the framework of this research programme, the institute is responsible for the two subprogrammes ''Plant and Reactor Safety'' and ''Thermal Fluid Dynamics'', respectively. We also provide minor contributions to the sub-programme ''Radio-Ecology''. Moreover, with the development of a pulsed photo-neutron source at the radiation source ELBE (Electron linear accelerator for beams of high brilliance and low emittance), we are involved in a networking project carried out by the FZR Institute of Nuclear and Hadron Physics, the Physics Department of TU Dresden, and ISR. (orig.)

  19. Fusion Safety Program annual report, fiscal year 1984

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.

    1985-06-01

    This report summarizes the Fusion Safety Program major activities in fiscal year 1984. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. A report section titled ''Activities at the INEL'' includes progress reports on the tritium implantation experiment, tritium blanket permeation, volatilization of reactor alloys, plasma disruptions, a comparative blanket safety assessment, transient code development, and a discussion of the INEL's participation in the Tokamak Fusion Core Experiment (TFCX) design study. The report section titled ''Outside Contracts'' includes progress reports on tritium conversion by the Oak Ridge National Laboratory (ORNL), lithium-lead reactions by the Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by MIT, tritium retention by the University of Virginia, and activation product release by GA Technologies. A list of publications produced during the year and brief descriptions of activities planned for FY-1985 are also included

  20. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1996

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F P; Rindelhardt, U [eds.

    1997-08-01

    The research of the institute aims at the safety assessment of the design of nuclear and chemical facilities, the development of accident management procedures, and the increase of operational safety by improved plant surveillance. Physical models and computer codes are developed for multiphase/multicomponent flows and for the space and time dependent power release in nuclear and chemical reactors to be able to analyse the thermo-fluiddynamic phenomena during assumed accident scenarios. Emphasis is particulary focussed on spatial flow phenomena and the time dependent change of flow patterns. Sustainable void fraction probes and tomographic systems are developed to measure those parameters of two phase flows that characterize the exchange of pulse, energy and mass between the phases and components. The research related to materials safety is directed to the behaviour of components exposed to neutron and gamma radiation. The susceptibility to irradiation induced embrittlement and the behaviour of annealed material during reirradiation are investigated by fracture mechanical methods in dependence on the materials composition. The work on process and plant diagnostics makes available basic methods for early failure detection and operational monitoring which are important means of accident prevention. Recent initiatives of the institute are concerned with the transport of pollutants in the geosphere. Particularly, codes are developed for the simulation of physical and chemical processes during the transport of pollutants in unsaturated zones of the soil. (orig.)

  1. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1996

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1997-08-01

    The research of the institute aims at the safety assessment of the design of nuclear and chemical facilities, the development of accident management procedures, and the increase of operational safety by improved plant surveillance. Physical models and computer codes are developed for multiphase/multicomponent flows and for the space and time dependent power release in nuclear and chemical reactors to be able to analyse the thermo-fluiddynamic phenomena during assumed accident scenarios. Emphasis is particularly focussed on spatial flow phenomena and the time dependent change of flow patterns. Sustainable void fraction probes and tomographic systems are developed to measure those parameters of two phase flows that characterize the exchange of pulse, energy and mass between the phases and components. The research related to materials safety is directed to the behaviour of components exposed to neutron and gamma radiation. The susceptibility to irradiation induced embrittlement and the behaviour of annealed material during reirradiation are investigated by fracture mechanical methods in dependence on the materials composition. The work on process and plant diagnostics makes available basic methods for early failure detection and operational monitoring which are important means of accident prevention. Recent initiatives of the institute are concerned with the transport of pollutants in the geosphere. Particularly, codes are developed for the simulation of physical and chemical processes during the transport of pollutants in unsaturated zones of the soil. (orig.)

  2. Annual and monthly range fidelity of female boreal woodland caribou in respons to petroleum development

    Directory of Open Access Journals (Sweden)

    Boyan V. Tracz

    2010-03-01

    Full Text Available Petroleum-sector development in northern Alberta, Canada has been implicated as one factor influencing the decline of boreal woodland caribou (Rangifer tarandus caribou. Previous research showed that caribou are farther from petroleum-sector disturbances within their home range than expected. As petroleum development increases, the distance caribou can selectively place themselves relative to industrial disturbance must decrease, because distances between disturbances decrease. Conceptually, the number of local disturbances becomes so large that caribou either abandon their local avoidance behaviour or leave their traditional home range. We evaluated whether an intense petroleum- development event in northern Alberta was sufficient to result in home range abandonment by female woodland caribou. Using well locations as an index of petroleum development, we found that caribou studied from 1992 to 2000 did not change their annual or monthly range fidelity as a function of development intensity. Caribou remained in peatland complexes containing a large number of petroleum-sector disturbances rather than move to new areas, presumably because the risks of dispersing across upland habitat to reach other suitable habitat are high. Such range fidelity may have fitness consequences for woodland caribou if they suffer greater predation in areas where petroleum development is occurring.

  3. Regulatory control of nuclear safety in Finland. Annual report 1999

    International Nuclear Information System (INIS)

    Tossavainen, K.

    2000-06-01

    This report concerns the regulatory control of nuclear energy in Finland in 1999. Its submission to the Ministry of Trade and Industry by the Finnish Radiation and Nuclear Safety Authority (STUK) is stipulated in section 121 of the Nuclear Energy Decree. STUK's regulatory work was focused on the operation of the Finnish nuclear power plants as well as on nuclear waste management and safeguards of nuclear materials. The operation of the Finnish nuclear power plants was in compliance with the conditions set out in their operating licences and with current regulations, with the exception of some inadvertent deviations from the Technical Specifications. No plant events endangering the safe use of nuclear energy occurred. The individual doses of all nuclear power plant workers remained below the dose threshold. The collective dose of the workers was low, compared internationally, and did not exceed STUK's guidelines at either nuclear power plant. The radioactive releases were minor and the dose calculated on their basis for the most exposed individual in the vicinity of the plant was well below the limit established in a decision of the Council of State at both Loviisa and Olkiluoto nuclear power plants. STUK issued statements to the Ministry of Trade and Industry about the environmental impact assessment programme reports on the possible nuclear power plant projects at Olkiluoto and Loviisa and about the continued operation of the research reactor in Otaniemi, Espoo. A Y2k-related safety assessment of the Finnish nuclear power plants was completed in December. In nuclear waste management STUK's regulatory work was focused on spent fuel storage and final disposal plans as well as on the treatment, storage and final disposal of reactor waste. No events occurred in nuclear waste management that would have endangered safety. A statement was issued to the Ministry of Trade and Industry about an environmental impact assessment report on a proposed final disposal facility for

  4. Regulatory control of nuclear safety in Finland. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Tossavainen, K. [ed.

    2000-06-01

    This report concerns the regulatory control of nuclear energy in Finland in 1999. Its submission to the Ministry of Trade and Industry by the Finnish Radiation and Nuclear Safety Authority (STUK) is stipulated in section 121 of the Nuclear Energy Decree. STUK's regulatory work was focused on the operation of the Finnish nuclear power plants as well as on nuclear waste management and safeguards of nuclear materials. The operation of the Finnish nuclear power plants was in compliance with the conditions set out in their operating licences and with current regulations, with the exception of some inadvertent deviations from the Technical Specifications. No plant events endangering the safe use of nuclear energy occurred. The individual doses of all nuclear power plant workers remained below the dose threshold. The collective dose of the workers was low, compared internationally, and did not exceed STUK's guidelines at either nuclear power plant. The radioactive releases were minor and the dose calculated on their basis for the most exposed individual in the vicinity of the plant was well below the limit established in a decision of the Council of State at both Loviisa and Olkiluoto nuclear power plants. STUK issued statements to the Ministry of Trade and Industry about the environmental impact assessment programme reports on the possible nuclear power plant projects at Olkiluoto and Loviisa and about the continued operation of the research reactor in Otaniemi, Espoo. A Y2k-related safety assessment of the Finnish nuclear power plants was completed in December. In nuclear waste management STUK's regulatory work was focused on spent fuel storage and final disposal plans as well as on the treatment, storage and final disposal of reactor waste. No events occurred in nuclear waste management that would have endangered safety. A statement was issued to the Ministry of Trade and Industry about an environmental impact assessment report on a proposed final

  5. Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994

    International Nuclear Information System (INIS)

    Hueper, R.

    1995-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  6. 77 FR 42176 - Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone

    Science.gov (United States)

    2012-07-18

    ... fireworks launch site located at position 41-34'-18.10'' N, 082-51'-18.70'' W (NAD 83). This zone will be... at position 41-34'-18.10'' N, 082- 51'-18.70'' W (NAD 83). (ii) Expected date. This safety zone will...-AA00 Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone AGENCY: Coast Guard...

  7. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F P; Rindelhardt, U [eds.

    1998-10-01

    The research work of the institute aims at the assessment and increase of the safety of technical facilities. Subject of the investigation are equally nuclear plants and installations of process industries. To analyse thermo-fluiddynamic phenomena of accident scenarios physical models and computer codes are developed as well for multi-phase and multi-component flows as for the time and space dependent power release (neutron kinetics in light water reactors, reaction kinetics of exothermic chemical reactions). Emphasis is put on the description of spatial flows and the transient evolution of flow patterns. (orig.)

  8. Fusion Safety Program annual report, fiscal year 1983

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.

    1984-07-01

    The Fusion Safety Program major activities for Fiscal Year 1983 are summarized in this report. The program was initiated in FY 1979, with the Idaho National Engineering Laboratory (INEL) designated lead laboratory, and EG and G Idaho, inc., named as prime contractor to implement this role. The report contains four sections: EG and G Idaho, Inc., activities at the INEL includes progress reports and portions of papers on the tritium implantation experiment, tritium control systems, tritium release from solid breeding blankets, plasma disruptions, risk assessment, transient code development, data base development, and a discussion of participation in the blanket comparison and selection study. The section outside contracts includes progress reports and portions of papers on lithium-lead reactions by Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by the University of California at Los Angeles (UCLA) and MIT, tritium retention by the University of Virginia, and effects of plasma disruptions by MIT. A list of publications and planned fiscal year 1984 activities are also included

  9. 1982 annual status report: safety of nuclear materials

    International Nuclear Information System (INIS)

    1982-01-01

    The JRC programme Safety of Nuclear Materials is essentially dealing with long-term safety aspects of radioactive waste which are of major importance for the solution of waste management problems. The main action of the JRC in relation to the waste management deals with the evaluation of long-term risks or geologic disposal, which is considered as one of the major issues of nuclear energy. In addition to the activity on risk evaluation of geologic disposal the JRC carries out activities which are related to fuel cycle optimization. They aim at indicating possible improvements in the many and complex operations of the fuel cycle, in order to obtain waste arisings which are optimized from a waste management point of view. Actinide separation from waste and extensive recycling of the separated actinides is a waste management option on which the JRC has been active for almost a decade and has acquired expertise and reputation. While the cost-benefit of such operations on high level waste appears doubtful the application of chemical partitioning to other waste streams appears as a promising way to maintain the α-waste arising at a reduced level without excessive sophistication of the technology of the fuel cycle

  10. Earthquake-associated events. Annual safety research report, JFY 2011

    International Nuclear Information System (INIS)

    2012-01-01

    For the tsunami and slope stability as the earthquake-associated events that increased with the revision of the regulatory guide for reviewing seismic design of nuclear power reactor facilities, related technical standard and analysis code were leveled up to support the safety examination of the country. For tsunami study, the original plan was changed due to the 2011 Tohoku earthquake tsunami, analysis code of river run-up, sedimentation, probabilistic tsunami hazard and tsunami trace database were developed. For slope study, in addition to conventional stress criteria, in order to build a slope stability evaluation method, incorporating new indicators, such as deformation and strain, the following study was conducted. The large-scale shaking table test for E-defense, the test data were obtained. The applicability of slope stability analysis code was examined by using the shaking table test data. (author)

  11. Radiation Protection and Safety Department - annual report 1977

    International Nuclear Information System (INIS)

    Kiefer, H.; Koelzer, W.

    1978-03-01

    The duties cover tasks relative to radiation protection and safety on behalf of the institutes and departments of Kernforschungszentrum Karlsruhe and environmental monitoring for the whole Nuclear Research Center as well as own research and development work, mainly performed under the Nuclear Research Center and the Nuclear Safeguards Project. The centers of interest of R and D activities were: investigation of the atmospheric diffusion in the micro- and meso-scale, study of the radiological consequences of accidents in reactors under probabilistic aspects, implementation of nuclear fuel safeguarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1977 routine measurements, and reports about new results of investigations and developments of the working groups of the department. (orig.) [de

  12. 49 CFR 659.25 - Annual review of system safety program plan and system security plan.

    Science.gov (United States)

    2010-10-01

    ... system security plan. 659.25 Section 659.25 Transportation Other Regulations Relating to Transportation... and system security plan. (a) The oversight agency shall require the rail transit agency to conduct an annual review of its system safety program plan and system security plan. (b) In the event the rail...

  13. 76 FR 37649 - Safety Zone; Northern California Annual Fireworks Events, Independence Day Fireworks

    Science.gov (United States)

    2011-06-28

    ... Zone; Northern California Annual Fireworks Events, Independence Day Fireworks AGENCY: Coast Guard, DHS... Independence Day Fireworks (Kings Beach 4th of July Fireworks) safety zone. This action is necessary to control... Fireworks in 33 CFR 165.1191 on July 3, 2011, from 7 a.m. through 10 p.m. The fireworks launch site is...

  14. Annual report 2002 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Janzekovic, H.; Stritar, A.

    2003-06-01

    The Slovenian Nuclear Safety Administration (SNSA) has prepared Annual Report on the Radiation and Nuclear Safety in the Republic of Slovenia for 2002. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. This report is different from the previous ones. The main part was shortened so that it can be easily read and understood. All details and numerous data are put into the extended report, which is available in the electronic form on an CD or at the home page of the Slovenian Nuclear Safety Administration. (author)

  15. Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

  16. Annual report 2002 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Janzekovic, H.; Stritar, A.

    2003-06-01

    The Slovenian Nuclear Safety Administration (SNSA) has prepared Annual Report on the Radiation and Nuclear Safety in the Republic of Slovenia for 2002. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. This report is different from the previous ones. The main part was shortened so that it can be easily read and understood. All details and numerous data are put into the extended report, which is available in the electronic form on an CD or at the home page of the Slovenian Nuclear Safety Administration.

  17. Industrial safety and applied health physics. Annual report, 1979

    International Nuclear Information System (INIS)

    1980-09-01

    In connection with personnel monitoring, there were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 55 employees received whole-body dose equivalent of one rem or greater. The highest whole-body dose equivalent to an employee was 2.8 rem. The highest internal exposure was less than one-half of a maximum permissible dose for any calendar quarter. During 1979, 57 portable health physics instruments were added to the inventory and 75 retired. The total number in service on January 1, 1979, was 977. With regards to environmental monitoring, there were no releases of gaseous waste from the Laboratory which were of a level that required an incident report to DOE. There were no releases of liquid radioactive waste from the Laboratory which were of a level that required an incident report to DOE. Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.01 to 0.06 pCi/g, and the uranium-235 content ranged from 0.01 to 0.05 pCi/g. Grass samples were collected at all perimeter and remote monitoring stations and analyzed for twelve radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.001 to 0.010 pCi/g, and uranium-235 content ranged from 0.001 to 0.010 pCi/g. Two radiation incidents involving radioactive materials were recorded during 1979. This compares with 14 incidents in 1978

  18. Industrial safety and applied health physics. Annual report, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    In connection with personnel monitoring, there were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 55 employees received whole-body dose equivalent of one rem or greater. The highest whole-body dose equivalent to an employee was 2.8 rem. The highest internal exposure was less than one-half of a maximum permissible dose for any calendar quarter. During 1979, 57 portable health physics instruments were added to the inventory and 75 retired. The total number in service on January 1, 1979, was 977. With regards to environmental monitoring, there were no releases of gaseous waste from the Laboratory which were of a level that required an incident report to DOE. There were no releases of liquid radioactive waste from the Laboratory which were of a level that required an incident report to DOE. Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.01 to 0.06 pCi/g, and the uranium-235 content ranged from 0.01 to 0.05 pCi/g. Grass samples were collected at all perimeter and remote monitoring stations and analyzed for twelve radionuclides including plutonium and uranium. Plutonium-239 content ranged from 0.001 to 0.010 pCi/g, and uranium-235 content ranged from 0.001 to 0.010 pCi/g. Two radiation incidents involving radioactive materials were recorded during 1979. This compares with 14 incidents in 1978. (ERB)

  19. Industrial safety and applied health physics. Annual report for 1978

    International Nuclear Information System (INIS)

    Auxier, J.A.

    1979-09-01

    There were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 39 employees received whole body dose equivalents of one rem or greater. The highest whole body dose equivalent to an employee was 3.3 rem. The highest internal exposure was less than 25% of a maximum permissible dose for any calendar quarter. During 1978, 23 portable instruments were added to the inventory and 228 retired. The total number in service on January 1, 1979, was 1023. There were no releases of gaseous waste or liquid radioactive waste from the laboratory which were of a level that required an incident report to DOE. The average background level at the PAM stations during 1978 was 9.3 μR/hr, or 81 mR/yr. Soil samples were collected at all perimeter and remote monitoring stations and analyzed for eleven radionuclides including plutonium and uranium. Grass samples were collected and analyzed for twelve radionuclides including plutonium and uranium. During 1978, the Radiation and Safety Surveys personnel continued to assist the operating groups in keeping contamination, air concentrations, and personnel exposure levels below the established maximum permissible levels. Fourteen radiation incidents involving radioactive materials were recorded during 1978. Of the 582,000 articles of wearing apparel and 192,000 articles, such as mops, laundry bags, towels, etc., monitored during 1978 about four percent were found to be contaminated. Three lost workday cases occurred at ORNL in 1978, a frequency rate of 0.07. The Serious Injury frequency rate for 1978 was 1.40, as based on the new OSHA system for recording injuries and illness (RII). A total of 55 days were lost or charged for the three lost workday cases in 1978

  20. Hellsgate Big Game Winter Range Wildlife Mitigation Project : Annual Report 2008.

    Energy Technology Data Exchange (ETDEWEB)

    Whitney, Richard P.; Berger, Matthew T.; Rushing, Samuel; Peone, Cory

    2009-01-01

    The Hellsgate Big Game Winter Range Wildlife Mitigation Project (Hellsgate Project) was proposed by the Confederated Tribes of the Colville Reservation (CTCR) as partial mitigation for hydropower's share of the wildlife losses resulting from Chief Joseph and Grand Coulee Dams. At present, the Hellsgate Project protects and manages 57,418 acres (approximately 90 miles2) for the biological requirements of managed wildlife species; most are located on or near the Columbia River (Lake Rufus Woods and Lake Roosevelt) and surrounded by Tribal land. To date we have acquired about 34,597 habitat units (HUs) towards a total 35,819 HUs lost from original inundation due to hydropower development. In addition to the remaining 1,237 HUs left unmitigated, 600 HUs from the Washington Department of Fish and Wildlife that were traded to the Colville Tribes and 10 secure nesting islands are also yet to be mitigated. This annual report for 2008 describes the management activities of the Hellsgate Big Game Winter Range Wildlife Mitigation Project (Hellsgate Project) during the past year.

  1. System and safety studies of accelerator driven transmutation systems. Annual report 1998

    International Nuclear Information System (INIS)

    Wallenius, J.; Gudowski, W.; Carlsson, Johan; Eriksson, Marcus; Tucek, K.

    1998-12-01

    This annual report describes the accelerator-driven transmutation project conducted at the Department of Nuclear and Reactor Physics at the Royal Institute of Technology. The main results are: development of the simulation tools for accelerator-driven transmutation calculations including an integrated Monte-Carlo burnup module and improvements of neutron energy fission yield simulations, processing of the evacuated nuclear data files including preparation of the temperature dependent neutron cross-sections, development of nuclear data for a medium energy range for some isotopes, development of the models and codes for radiation damage simulations, system studies for the spent fuel transmuter, based on heavy metal coolant and advanced nuclear fuel, contribution to the spallation target design being manufactured in IPPE, Obninsk, and accelerator reliability studies. Moreover a lot of efforts were put to further develop existing international collaboration with the most active research groups in the world together with educational activities in Sweden including a number of meetings and workshops and a graduate course in transmutation. This project has been conducted in close collaboration with the EU-project 'Impact of the accelerator based technologies on nuclear fission safety' - IABAT and in bilateral cooperation with different foreign research groups

  2. System and safety studies of accelerator driven transmutation systems. Annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Wallenius, J.; Gudowski, W.; Carlsson, Johan; Eriksson, Marcus; Tucek, K. [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    1998-12-01

    This annual report describes the accelerator-driven transmutation project conducted at the Department of Nuclear and Reactor Physics at the Royal Institute of Technology. The main results are: development of the simulation tools for accelerator-driven transmutation calculations including an integrated Monte-Carlo burnup module and improvements of neutron energy fission yield simulations, processing of the evacuated nuclear data files including preparation of the temperature dependent neutron cross-sections, development of nuclear data for a medium energy range for some isotopes, development of the models and codes for radiation damage simulations, system studies for the spent fuel transmuter, based on heavy metal coolant and advanced nuclear fuel, contribution to the spallation target design being manufactured in IPPE, Obninsk, and accelerator reliability studies. Moreover a lot of efforts were put to further develop existing international collaboration with the most active research groups in the world together with educational activities in Sweden including a number of meetings and workshops and a graduate course in transmutation. This project has been conducted in close collaboration with the EU-project `Impact of the accelerator based technologies on nuclear fission safety` - IABAT and in bilateral cooperation with different foreign research groups 31 refs, 23 figs

  3. Calendar year 2007 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii,

    Energy Technology Data Exchange (ETDEWEB)

    Agogino, Karen [Department of Energy, Albuquerque, NM (United States). National Nuclear Security Administration (NNSA); Sanchez, Rebecca [Sandia Corp., Albuquerque, NM (United States)

    2008-09-30

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation (Sandia), a wholly owned subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE)/National Nuclear Security Administration (NNSA), through the Sandia Site Offi ce (SSO), in Albuquerque, NM, administers the contract and oversees contractor operations at TTR and KTF. Sandia manages and conducts operations at TTR in support of the DOE/NNSA’s Weapons Ordnance Program and has operated the site since 1957. Washington Group International subcontracts to Sandia in administering most of the environmental programs at TTR. Sandia operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2007. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia is responsible only for those environmental program activities related to its operations. The DOE/NNSA/Nevada Site Offi ce (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2007a) and DOE Manual 231.1-1A, Environment, Safety, and Health Reporting Manual (DOE 2007).

  4. Calendar year 2002 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

    2003-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, oversees TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2002. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 5400.1, General Environmental Protection Program (DOE 1990) and DOE Order 231.1, Environment, Safety, and Health Reporting (DOE 1996).

  5. 2013 Annual Site Environmental Report for Sandia National Laboratories Tonopah Test Range Nevada & Kauai Test Facility Hawaii

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, Stacy Rene [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Agogino, Karen [National Nuclear Security Administration (NNSA), Washington, DC (United States); Li, Jun [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); White, Nancy [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Minitrez, Alexandra [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Avery, Penny [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Bailey-White, Brenda [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Bonaguidi, Joseph [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Catechis, Christopher [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); duMond, Michael [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Eckstein, Joanna [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Evelo, Stacie [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Forston, William [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Herring, III, Allen [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Lantow, Tiffany [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Martinez, Reuben [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Mauser, Joseph [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Miller, Amy [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Miller, Mark [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Payne, Jennifer [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Peek, Dennis [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Reiser, Anita [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Ricketson, Sherry [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Roma, Charles [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Salinas, Stephanie [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Ullrich, Rebecca [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2014-08-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities managed and operated by Sandia Corporation (Sandia), a wholly owned subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Field Office (SFO), in Albuquerque, New Mexico, administers the contract and oversees contractor operations at TTR and KTF. Sandia manages and conducts operations at TTR in support of the DOE/NNSA’s Weapons Ordnance Program and has operated the site since 1957. Navarro Research and Engineering subcontracts to Sandia in administering most of the environmental programs at TTR. Sandia operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report summarizes data and the compliance status of the sustainability, environmental protection, and monitoring program at TTR and KTF through Calendar Year 2013. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, Environmental Restoration (ER) cleanup activities, and the National Environmental Policy Act. Sandia is responsible only for those environmental program activities related to its operations. The DOE/NNSA/Nevada Field Office retains responsibility for the cleanup and management of TTR ER sites. Environmental monitoring and surveillance programs are required by DOE Order 231.1B, Environment, Safety, and Health Reporting (DOE 2012).

  6. Proceedings of Twenty-Seventh Annual Institute on Mining Health, Safety and Research

    Energy Technology Data Exchange (ETDEWEB)

    Bockosh, G.R. [ed.] [Pittsburgh Research Center, US Dept. of Energy (United States); Langton, J. [ed.] [Mine Safety and Health Administration, US Dept. of Labor (United States); Karmis, M. [ed.] [Virginia Polytechnic Institute and State University. Dept. of Mining and Minerals Engineering, Blacksburg (United States)

    1996-12-31

    This Proceedings contains the presentations made during the program of the Twenty-Seventh Annual Institute on Mining Health, Safety and Research held at Virginia Polytechnic Institute and State University, Blacksburg, Virginia, on August 26-28, 1996. The Twenty-Seventh Annual Institute on Mining, Health, Safety and Research was the latest in a series of conferences held at Virginia Polytechnic Institute and State University, cosponsored by the Mine Safety and Health Administration, United States Department of Labor, and the Pittsburgh Research Center, United States Department of Energy (formerly part of the Bureau of Mines, U. S. Department of Interior). The Institute provides an information forum for mine operators, managers, superintendents, safety directors, engineers, inspectors, researchers, teachers, state agency officials, and others with a responsible interest in the important field of mining health, safety and research. In particular, the Institute is designed to help mine operating personnel gain a broader knowledge and understanding of the various aspects of mining health and safety, and to present them with methods of control and solutions developed through research. Selected papers have been processed separately for inclusion in the Energy Science and Technology database.

  7. Annual plan of research on safety techniques against low level radioactive wastes, 1984-1988

    International Nuclear Information System (INIS)

    1984-01-01

    The establishment of the countermeasures for treating and disposing radioactive wastes has become an important subject for promoting the utilization of atomic energy. Especially as to low level radioactive wastes, the cumulative quantity has reached about 460,000 in terms of 200 l drums as of the end of March, 1983, and accompanying the development of the utilization of atomic energy, its rapid increase is expected. So far, as for the disposal of low level radioactive wastes, the research and development and the preparation of safety criteria and safety evaluation techniques have been carried out, following the basic policy of the Atomic Energy Commission to execute land disposal and ocean disposal in combination, first to make the test disposal after preliminary safety evaluation, and to shift to the full scale disposal based on the results. The annual plan was decided on July 22, 1983, and the first revision was carried out this time, therefore, it is reported here. The basic policy of establishing this annual plan, and the annual plan for safety technique research are described. (Kako, I.)

  8. Germination of Winter Annual Grass Weeds under a Range of Temperatures and Water Potentials

    DEFF Research Database (Denmark)

    Scherner, Ananda; Melander, Bo; Jensen, Peter Kryger

    2017-01-01

    Silky windgrass and annual bluegrass are among the most troublesome weeds in northern European winter crops, while problems with rattail fescue have been especially linked to direct-drilling practices. This study investigated the germination patterns of silky windgrass, annual bluegrass, and ratt...

  9. 78 FR 53675 - Eighth Coast Guard District Annual Safety Zones; Boomsday Festival; Tennessee River 646.0-649.0...

    Science.gov (United States)

    2013-08-30

    ...-AA00 Eighth Coast Guard District Annual Safety Zones; Boomsday Festival; Tennessee River 646.0-649.0... Guard will enforce a Safety Zone for the Boomsday Festival Fireworks on the Tennessee River 646.0-649.0... Festival Fireworks. During the enforcement period, entry into, transiting or anchoring in the Safety Zone...

  10. 75 FR 35652 - Safety Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, South Lake...

    Science.gov (United States)

    2010-06-23

    ... Zone; Northern California Annual Fireworks Events, Fourth of July Fireworks, South Lake Tahoe Gaming... will enforce Lights on the Lake Fireworks Display safety zone for South Lake Tahoe, from 8:30 a.m. on... the Lake Fireworks in 33 CFR 165.1191 on July 4, 2010, from 8:30 a.m. on July 1, 2010 through 10 p.m...

  11. AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

    International Nuclear Information System (INIS)

    Oursel, Luc; Riou, Jean

    2014-06-01

    This annual report by AREVA's General Inspectorate deals with the status of nuclear safety and radiation protection in the group's facilities and operations over the course of 2013. Based on the findings made during implementation of the annual inspection program, this annual report also includes the results of the analysis of significant events and the observations and assessments of specialists in the Safety Health Security Sustainable Development Department (SHSSDD), supplemented by regular interaction with the safety regulators, different government agencies, stakeholders and other nuclear operators. Additionally, this report presents the action plans put into motion and the directions taken for continuous improvement in risk prevention for operations conducted in France and internationally. In 2013, the level of safety in the group's nuclear facilities and operations remained satisfactory, although improvements are necessary in some domains. This report is based on established indicators, analyses of reported events, responses to commitments made to the regulators, and the results of different improvement actions reported on in the inspected and supported entities. In 2013, no level 2 event on the International Nuclear and Radiological Event Scale (INES) was reported, the bottom-up reporting of weak signals was confirmed, dose levels were low and there were no radiological impacts on the environment. The General Inspectorate conducted 45 inspections in 30 of the group's entities in 2013. Of these, 10 concerned sites outside France and 7 were conducted following events or particular situations. These inspections gave rise to 176 recommendations, which the inspected entities have translated into action plans. Verification of these different action plans according to planned procedures and announced schedules gave rise to 16 follow-up inspections. The major lessons learned from these inspections relate to project management, facility compliance and operational

  12. Annual report of the Chief Executive Officer of the Australian Radiation Protection and Nuclear Safety Agency 2005-06

    International Nuclear Information System (INIS)

    2005-01-01

    This report satisfies the annual reporting requirements of the ARPANS Act in addition to the Department of Prime Minister and Cabinet requirements for annual reporting by Agencies. The report includes: details of the operations of the CEO and details of directions given by the Minister under section 16 at Part 1; details of the operations of ARPANSA at Part 3; details of the operations of the Radiation Health Advisory Council, the Radiation Health Committee and the Nuclear Safety Committee and details of all reports received from the Radiation Health and Safety Advisory Council on matters related to radiation protection and nuclear safety or the Nuclear Safety Committee on matters related to nuclear safety and the safety of controlled facilities at Part 4; details of any breach of licence conditions by a licensee at Appendix 4; an index of compliance with the annual reporting requirements at Appendix 8

  13. Pacific Northwest Laboratory annual report for 1989 to the Assistant Secretary for Environment, Safety, and Health

    International Nuclear Information System (INIS)

    Faust, L.G.; Doctor, P.G.; Selby, J.M.

    1990-04-01

    Part 5 of the 1989 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, the Office of National Environmental Policy Act Project Assistance, the Office of Nuclear Safety, the Office of Safety Compliance, and the Office of Policy and Standards. For each project, as identified by the Field Work Proposal, there is an article describing progress made during fiscal year 1989. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work. 35 refs., 1 fig

  14. Pacific Northwest Laboratory annual report for 1990 to the Assistant Secretary for Environment, Safety, and Health

    International Nuclear Information System (INIS)

    Faust, L.G.; Moraski, R.V.; Selby, J.M.

    1991-05-01

    Part 5 of the 1990 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Guidance, the Office of Environmental Compliance, the Office of Environmental Audit, the Office of National Environmental Policy Act Project Assistance, the Office of Nuclear Safety, the Office of Safety Compliance, and the Office of Policy and Standards. For each project, as identified by the Field Work Proposal, there is an article describing progress made during fiscal year 1990. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work

  15. 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)

  16. Fourth Annual Nursing Leadership Congress: "Driving Patient Safety Through Transformation" Conference proceedings.

    Science.gov (United States)

    Pinakiewicz, Diane; Smetzer, Judy; Thompson, Pamela; Navarra, Mary Beth; Lambert, Monique

    2009-06-01

    In September 2008, nurse executives from around the country met in Scottsdale, Ariz, to develop practical tools and recommendations for "Driving Patient Safety Through Transformation," the theme of the fourth annual Nursing Leadership Congress. The Congress was made possible through an educational grant from McKesson and Intel in collaboration with sponsorship from the American Organization of Nurse Executives, Institute for Safe Medication Practices and National Patient Safety Foundation. This paper summarizes the Congress plenary sessions and roundtable discussions. Plenaries included the following: *Transformational Leadership: The Role of Leaders in Managing Complex Problems *Using the Baldrige Business Model as the Infrastructure for Creating a Culture of Patient Safety *Prospects for Structural Reform in Health Care Roundtables included the following: *Joy and Meaning in Work *Managing Chronic Care Across the Continuum *The Future of Acute Care Delivery in Light of Changing Reimbursement* Leveraging Transparency to Drive Patient Safety *Collaborative Partnerships for Driving a Patient Safety Agenda *Innovative Solutions for Patient Safety *Implementing the Fundamentals of the Toyota Production Model forHealthcare

  17. Annual report on reactor safety research projects. Reporting period 2013. Progress report

    International Nuclear Information System (INIS)

    2013-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  18. Annual report on reactor safety research projects. Reporting period 2011. Progress report

    International Nuclear Information System (INIS)

    2011-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  19. Annual report on reactor safety research projects. Reporting period 2014. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. lt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  20. Annual report on reactor safety research projects. Reporting period 2015. Progress report

    International Nuclear Information System (INIS)

    2015-01-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft tor Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are ·' prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. it has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  1. Atomic safety and licensing board panel: Annual report, Fiscal Year 1988

    International Nuclear Information System (INIS)

    1989-03-01

    This is the fiscal year 1988 annual report of the Atomic Safety and Licensing Board Panel. In response to further reduction in is authorized staffing level and with an eye toward the proposed full- text, electronic docket of the expected High-Level Waste Repository proceedings, the Panel stepped up efforts during fiscal year 1988 to extend the scope, depth and availability of its Computer Assistance Project (CAP) through INQUIRE. INQUIRE, and the Panel's ability to use the system to expeditiously manage and search the massive records that characterize our most complex cases, has generated great interest among legal practitioners and adjudicatory bodies throughout the United States and Canada

  2. 76 FR 26931 - Safety Zone; Second Annual Space Coast Super Boat Grand Prix, Atlantic Ocean, Cocoa Beach, FL

    Science.gov (United States)

    2011-05-10

    ...-AA00 Safety Zone; Second Annual Space Coast Super Boat Grand Prix, Atlantic Ocean, Cocoa Beach, FL... temporary safety zone on the waters of the Atlantic Ocean east of Cocoa Beach, Florida during the Second... Atlantic Ocean east of Cocoa Beach, Florida. Approximately 30 high-speed power boats will be participating...

  3. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key topic / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Traichel, Anke [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany). Dept. of Safety Engineering and Assessment / Proposals Engineering

    2017-04-15

    Summary report on the Key Topic ''Enhanced Safety and Operation Excellence'' Technical Session ''Safety, IT, Hazards and PSA'' of the 47th Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016.

  4. 77 FR 37318 - Eighth Coast Guard District Annual Safety Zones; Sound of Independence; Santa Rosa Sound; Fort...

    Science.gov (United States)

    2012-06-21

    ...-AA00 Eighth Coast Guard District Annual Safety Zones; Sound of Independence; Santa Rosa Sound; Fort... Coast Guard will enforce a Safety Zone for the Sound of Independence event in the Santa Rosa Sound, Fort... during the Sound of Independence. During the enforcement period, entry into, transiting or anchoring in...

  5. 78 FR 77359 - Eighth Coast Guard District Annual Safety Zones; New Year's Eve Celebration/City of Mobile...

    Science.gov (United States)

    2013-12-23

    ...-AA00 Eighth Coast Guard District Annual Safety Zones; New Year's Eve Celebration/City of Mobile; Mobile Channel; Mobile, AL AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard will enforce the City of Mobile New Year's Eve Celebration safety zone in the Mobile Channel, Mobile, AL from...

  6. 2004 annual report. Defense, safety, energy, information, health. CEA in the center of big European challenges

    International Nuclear Information System (INIS)

    2005-01-01

    This document is the 2004 annual report of the French atomic energy commission (CEA). It presents the R and D activities of the CEA in three main domains: 1 - defense and safety, maintaining perenniality of nuclear dissuasion and nuclear safety: supplying nuclear weapons to armies, maintaining dissuasion capability with the simulation program, sharing R and D means with the scientific community and the industrial world, designing and maintaining naval nuclear propulsion reactors, cleansing Marcoule and Pierrelatte facilities, monitoring treaties and fighting against proliferation and terrorism; 2 - energy, developing more competitive and cleaner energy sources: nuclear waste management, optimization of industrial nuclear activities, future nuclear systems and new energy technologies, basic research on energy, radiobiology and toxicology; 3 - information and health, valorizing industry thanks to technological research and supplying new tools for health and medical research: micro- and nano-technologies, software technologies, basic research for industrial innovation, nuclear technologies for health and bio-technologies. (J.S.)

  7. Safety

    International Nuclear Information System (INIS)

    2001-01-01

    This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

  8. Ferrocyanide Safety Project Task 3 Ferrocyanide Aging Studies FY 1993 annual report

    International Nuclear Information System (INIS)

    Lilga, M.A.; Lumetta, M.R.; Schiefelbein, G.F.

    1993-10-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. The Ferrocyanides Safety Project at PNL is part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, sponsored by the US Department of Energy's Tank Farm Project Office, is to (1) maintain the ferrocyanide tanks with minimal risk of an accident, (2) select one or more strategies to assure safe storage, and (3) close out the unreviewed safety question (USQ). This annual report gives the results of the work conducted by PNL in FY 1993 on Task 3, Ferrocyanides Aging Studies, which deals with the aging behavior of simulated ferrocyanide wastes. Aging processes include the dissolution and hydrolysis of nickel ferrocyanides in high pH aqueous solutions. Investigated were the effects of pH variation; ionic strength and sodium ion concentration; the presence of anions such as phosphate, carbonate, and nitrate; temperature; and gamma radiation on solubility of ferrocyanide materials including In-Farm-lA, Rev. 4 flowsheet-prepared Na 2 NiFe(CN) 6

  9. Trends in safety pharmacology: posters presented at the annual meetings of the Safety Pharmacology Society 2001-2010.

    Science.gov (United States)

    Redfern, William S; Valentin, Jean-Pierre

    2011-01-01

    The inaugural meeting of the Safety Pharmacology Society (SPS) was in 2001, soon after ICH S7A had been adopted. The 10th anniversary is an appropriate milestone at which to analyse trends in the science and themes of safety pharmacology, as reflected in posters presented at the annual meetings. The source information was the poster abstract booklets from each of the first ten annual meetings. The number of posters rose steadily from 34 in 2001 to 201 in 2010. The proportion of posters containing in vitro data has remained constant throughout the decade at ~30%. In terms of organ functions, themes relating to the cardiovascular system (CVS) have always generated the majority of posters, remaining above 60% of the total for the last 9years. The dominant theme has been around 'QT liability'. This peaked in 2003 at 68% of all posters presented, around the time of the ICHS7B discussions, and has remained above 30% thereafter. Apart from 2003 (dipping to 4%), CNS-related posters have remained steady at 11-17% throughout the decade. Respiratory-related posters have remained at 5-8% over the last 5years. Gastrointestinal (GI)-related posters have contributed 2-6% throughout the decade, and renal-related posters 1-3%. Posters on combined organ assessments have appeared in recent years. The relative emphasis on the different organ functions is broadly proportional to the causes of candidate drug attrition preclinically, whereas both CNS and GI are under-represented when considering their contribution to significant adverse effects during clinical development. Trends are either regulatory-driven (e.g. increase in posters on abuse-dependence liability since EMEA/CHMP/SWP/94227/2004), technology-driven (e.g. automated hERG assay; left ventricular function; non-invasive CVS measurements; stem cells, etc.), or relate to the predictive ability of safety pharmacology data (e.g. clinical translation initiatives; concordance between in vitro and in vivo preclinical data; integrated

  10. Proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management 2005 Kyoto

    International Nuclear Information System (INIS)

    2005-01-01

    This is the program and the proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management held from November 23rd through the 25th of 2005. The sessions held were: (1) Medical Exposure, (2) Environmental Measurement and Radiation Source Handling, (3) Radiation Measurement and Influence of Electromagnetic Waves, (4) Utilization of Irradiation, (5) Countermeasures against Contamination and Inspection of Contamination, (6) Imaging Plate, (7) Controlled Measurement and Dose Evaluation, (8) Working Environment Measurement 1, (9) Working Environment Measurement 2, (10) Establishment of Software and System, (11) Radiation Education 1, (12) Radiation Education 2, and (13) Exposure Reduction and Safety Control. The poster sessions held were: (1) Exposure Reduction and Radiation Evaluation, (2) Radiation Measurement and Influence of Electromagnetic Waves, (3) Education Training, (4) Safety Control, (5) Software, Data Handling, and Shielding Calculation, and (6) Environmental Radioactivity. The keynote lectures held were: (1) 'Situation of Medical Exposure' and (2) 'Cosmic Radiation While Boarding on Airplanes'. The symposia held were: (1) 'Food Irradiation' and (2) 'Life Science'. (S.K.)

  11. Reduced pollinator service and elevated pollen limitation at the geographic range limit of an annual plant.

    Science.gov (United States)

    Moeller, David A; Geber, Monica A; Eckhart, Vincent M; Tiffin, Peter

    2012-05-01

    Mutualisms are well known to influence individual fitness and the population dynamics of partner species, but little is known about whether they influence species distributions and the location of geographic range limits. Here, we examine the contribution of plant-pollinator interactions to the geographic range limit of the California endemic plant Clarkia xantiana ssp. xantiana. We show that pollinator availability declined from the center to the margin of the geographic range consistently across four years of study. This decline in pollinator availability was caused to a greater extent by variation in the abundance of generalist rather than specialist bee pollinators. Climate data suggest that patterns of precipitation in the current and previous year drove variation in bee abundance because of its effects on cues for bee emergence in the current year and the abundance of floral resources in the previous year. Experimental floral manipulations showed that marginal populations had greater outcross pollen limitation of reproduction, in parallel with the decline in pollinator abundance. Although plants are self-compatible, we found no evidence that autonomous selfing contributes to reproduction, and thus no evidence that it alleviates outcross pollen limitation in marginal populations. Furthermore, we found no association between the distance to the range edge and selfing rate, as estimated from sequence and microsatellite variation, indicating that the mating system has not evolved in response to the pollination environment at the range periphery. Overall, our results suggest that dependence on pollinators for reproduction may be an important constraint limiting range expansion in this system.

  12. Annual report for FY 2011 on the activities of radiation safety in J-PARC

    International Nuclear Information System (INIS)

    2013-02-01

    This annual report describes the activities of radiation safety of Japan Proton Accelerator Research Complex (J-PARC) for FY 2011. The activities described are radiation protection in workplaces, environmental monitoring, individual monitoring, maintenance of monitoring instruments, and the technological developments of radiation protection. Occupational exposures have not exceeded the prescribed dose limit. No effluent releases were recorded exceeding the prescribed limits on the amount and concentration of radioactivity for gaseous release and liquid waste. J-PARC was suffered from the Great East Japan Earthquake and the accident at the Fukushima Daiichi Nuclear Power Plant. The report also covers the activities for the recovery of J-PARC and the environmental monitoring of radioactivity from the accident. (author)

  13. Annual report for FY 2011 on the activities of radiation safety in J-PARC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-02-15

    This annual report describes the activities of radiation safety of Japan Proton Accelerator Research Complex (J-PARC) for FY 2011. The activities described are radiation protection in workplaces, environmental monitoring, individual monitoring, maintenance of monitoring instruments, and the technological developments of radiation protection. Occupational exposures have not exceeded the prescribed dose limit. No effluent releases were recorded exceeding the prescribed limits on the amount and concentration of radioactivity for gaseous release and liquid waste. J-PARC was suffered from the Great East Japan Earthquake and the accident at the Fukushima Daiichi Nuclear Power Plant. The report also covers the activities for the recovery of J-PARC and the environmental monitoring of radioactivity from the accident. (author)

  14. First NASA Aviation Safety Program Weather Accident Prevention Project Annual Review

    Science.gov (United States)

    Colantonio, Ron

    2000-01-01

    The goal of this Annual Review was to present NASA plans and accomplishments that will impact the national aviation safety goal. NASA's WxAP Project focuses on developing the following products: (1) Aviation Weather Information (AWIN) technologies (displays, sensors, pilot decision tools, communication links, etc.); (2) Electronic Pilot Reporting (E-PIREPS) technologies; (3) Enhanced weather products with associated hazard metrics; (4) Forward looking turbulence sensor technologies (radar, lidar, etc.); (5) Turbulence mitigation control system designs; Attendees included personnel from various NASA Centers, FAA, National Weather Service, DoD, airlines, aircraft and pilot associations, industry, aircraft manufacturers and academia. Attendees participated in discussion sessions aimed at collecting aviation user community feedback on NASA plans and R&D activities. This CD is a compilation of most of the presentations presented at this Review.

  15. U.S. Department of Energy NESHAP Annual Report for CY 2014 Sandia National Laboratories Tonopah Test Range

    Energy Technology Data Exchange (ETDEWEB)

    Evelo, Stacie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Miller, Mark L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-05-01

    This National Emission Standards for Hazardous Air Pollutants (NESHAP) Annual Report has been prepared in a format to comply with the reporting requirements of 40 CFR 61.94 and the April 5, 1995 Memorandum of Agreement (MOA) between the Department of Energy (DOE) and the Environmental Protection Agency (EPA). According to the EPA approved NESHAP Monitoring Plan for the Tonopah Test Range (TTR), 40 CFR 61, subpart H, and the MOA, no additional monitoring or measurements are required at TTR in order to demonstrate compliance with the NESHAP regulation.

  16. Atomic Safety and Licensing Board Panel annual report, fiscal year 1989

    International Nuclear Information System (INIS)

    Cotter, B.P. Jr.

    1990-07-01

    In Fiscal Year 1989, the Atomic Safety and Licensing Board Panel (ASLBP) handled 40 proceedings involving the construction, operation and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights and analyzes how the wide-ranging issues raised in these proceedings were addressed by the Judges and Licensing Boards of the ASLBP during the year. 5 figs., 3 tabs

  17. Atomic Safety and Licensing Board Panel annual report, Fiscal year 1992

    International Nuclear Information System (INIS)

    1993-09-01

    In Fiscal Year 1992, the Atomic Safety and Licensing Board Panel (''the Panel'') handled 38 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license from the Nuclear Regulatory Commission. This reports sets out the Panel's caseload during the year and summarizes, highlights, and analyzes how the wide-ranging issues raised in those proceedings were addressed by the Panel's judges and licensing boards

  18. Pacific Northwest Laboratory: Annual report for 1986 to the Assistant Secretary for Environment, Safety and Health: Part 5, Nuclear and operational safety

    International Nuclear Information System (INIS)

    Faust, L.G.; Kennedy, W.E.; Steelman, B.L.; Selby, J.M.

    1987-02-01

    Part 5 of the 1986 Annual Report to the Department of Energy's Assistant Secretary for Environment, Safety and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety, the Office of Operational Safety, and for the Office of Environmental Analysis. For each project, as identified by the Field Task Proposal/Agreement, articles describe progress made during fiscal year 1986. Authors of these articles represent a broad spectrum of capabilities derived from three of the seven research departments of the Laboratory, reflecting the interdisciplinary nature of the work

  19. Proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management 2006 Nagoya

    International Nuclear Information System (INIS)

    2006-01-01

    This is the program and the proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management held from November 29th through December 1st of 2006. The sessions held are: (1) Radiation Measurement 1, (2) Education Method, (3) Radiation Control, (4) Waste Handling, Contamination Inspection, and Renewal, (5) Exposure Reduction, Radiation Evaluation, and Radioactivity Control (6) Radiation Measurement 2, (7) Operation Environment, (8) Medical Exposure, (9) Radiation Measurement 3, (10) Software, IT Technology, and Data Processing, (11) Emission and Drainage Handling, and (12) Radiation Effect and Contamination Countermeasure. The poster sessions held are: (1) Radiation Measurement, (2) Environmental Radiation, (3) Scattering Rate, Penetration Rate, and Contamination Inspection, (4) Education Method, (5) Medical Exposure, (6) Access Control and Software, and (7) Radiation Control Method and Monitoring. The symposia held are: (1) 'Toward Establishment of Guideline for Safe X-ray Handling Education' and 'International Situation of Radiation Safety'. 2 keynote lectures were also held. (S.K.)

  20. Industrial Safety and Applied Health Physics Division annual report for 1981

    International Nuclear Information System (INIS)

    Auxier, J.A.; Oakes, T.W.

    1982-08-01

    Activities over the past year are summarized for the Health Physics Department, the Environmental Management Program, and the Safety Department. The Health Physics Department conducts radiation and safety surveys, provides personnel monitoring services for both external and internal radiation, and procures, services, and calibrates appropriate portable and stationary health physics instruments. It was determined that the maximum whole-body dose sustained by an employee was about 3.8 rems, which is 76% of the applicable standard of 5 rems. The greatest cumulative dose to the skin of the whole body received by an employee during 1981 was about 5.9 rems, or 39% of the applicable standard of 15 rems. Atmospheric iodine sampled by the Department of Environmental Management at the perimeter stations averged 0.13E to 14 μCi/cc during 1981. This average represents 131 I released to uncontrolled areas. All air samples taken had values below the allowable standards. The concentrations of 90 Sr in milk from both the immediate and remote environs of ORNL are also within FRC range I. The average value of 1.5 E to 9 μCi/mL represents 0.5% of the CG/sub w/ for drinking water applicable to individuals in the general population. The Safety Department reported that the continuing emphasis on safety during CY 1981 resulted in significant improvements in the ORNL safety program: safety performance was better than all CY 1981 on-the-job injury and illness goals. Through December 31, 1981, the Laboratory had worked 600 days and accumulated 14,015,826 exposure-hours since the last lost-work-day case

  1. Industrial Safety and Applied Health Physics Division annual report for 1981

    Energy Technology Data Exchange (ETDEWEB)

    Auxier, J.A.; Oakes, T.W.

    1982-08-01

    Activities over the past year are summarized for the Health Physics Department, the Environmental Management Program, and the Safety Department. The Health Physics Department conducts radiation and safety surveys, provides personnel monitoring services for both external and internal radiation, and procures, services, and calibrates appropriate portable and stationary health physics instruments. It was determined that the maximum whole-body dose sustained by an employee was about 3.8 rems, which is 76% of the applicable standard of 5 rems. The greatest cumulative dose to the skin of the whole body received by an employee during 1981 was about 5.9 rems, or 39% of the applicable standard of 15 rems. Atmospheric iodine sampled by the Department of Environmental Management at the perimeter stations averged 0.13E to 14 ..mu..Ci/cc during 1981. This average represents < 0.005% of the concentration guide of 1E to 10 ..mu..Ci/cc applicable to inhalation of /sup 131/I released to uncontrolled areas. All air samples taken had values below the allowable standards. The concentrations of /sup 90/Sr in milk from both the immediate and remote environs of ORNL are also within FRC range I. The average value of 1.5 E to 9 ..mu..Ci/mL represents 0.5% of the CG/sub w/ for drinking water applicable to individuals in the general population. The Safety Department reported that the continuing emphasis on safety during CY 1981 resulted in significant improvements in the ORNL safety program: safety performance was better than all CY 1981 on-the-job injury and illness goals. Through December 31, 1981, the Laboratory had worked 600 days and accumulated 14,015,826 exposure-hours since the last lost-work-day case.

  2. 8th Annual report 1999. UN ECE convention on long-range transboundary air pollution

    Energy Technology Data Exchange (ETDEWEB)

    Kleemola, S.; Forsius, M. [eds.

    1999-07-01

    The Integrated Monitoring Programme (ICP IM) is part of the Effects Monitoring Strategy under the UN ECE Convention on Long-Range Transboundary Air Pollution. The main aim of ICP IM is to provide a framework to observe and understand the complex changes occurring in the external environment. This report summarizes the work carried out by the ICP IM Programme Centre and several collaborating institutes. The emphasis of the report is in the work done during the programme year 1998/99 including: - a short summary of previous data assessments - a short status report of the ICP IM activities, content of the IM database, and the present geographical coverage of the monitoring network - a documentation of the scientific strategies to carry out data assessment on two priority topics: - assessment of heavy metal pools and fluxes - assessment of cause-effect relationships for understorey vegetation - a description of the WATBAL-model for estimating monthly water balance components, including soil water fluxes. (orig.)

  3. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Bohnstedt, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Programm Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE); Baumann, Erik [AREVA GmbH, Erlangen (Germany). Radiation Protection

    2016-12-15

    Summary report on the Key Topic 'Enhanced Safety and Operation Excellence' Focus Session 'Radiation Protection' of the 47{sup th} Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

  4. Ares-I-X Vehicle Preliminary Range Safety Malfunction Turn Analysis

    Science.gov (United States)

    Beaty, James R.; Starr, Brett R.; Gowan, John W., Jr.

    2008-01-01

    Ares-I-X is the designation given to the flight test version of the Ares-I rocket (also known as the Crew Launch Vehicle - CLV) being developed by NASA. As part of the preliminary flight plan approval process for the test vehicle, a range safety malfunction turn analysis was performed to support the launch area risk assessment and vehicle destruct criteria development processes. Several vehicle failure scenarios were identified which could cause the vehicle trajectory to deviate from its normal flight path, and the effects of these failures were evaluated with an Ares-I-X 6 degrees-of-freedom (6-DOF) digital simulation, using the Program to Optimize Simulated Trajectories Version 2 (POST2) simulation framework. The Ares-I-X simulation analysis provides output files containing vehicle state information, which are used by other risk assessment and vehicle debris trajectory simulation tools to determine the risk to personnel and facilities in the vicinity of the launch area at Kennedy Space Center (KSC), and to develop the vehicle destruct criteria used by the flight test range safety officer. The simulation analysis approach used for this study is described, including descriptions of the failure modes which were considered and the underlying assumptions and ground rules of the study, and preliminary results are presented, determined by analysis of the trajectory deviation of the failure cases, compared with the expected vehicle trajectory.

  5. On the long-range dependence properties of annual precipitation using a global network of instrumental measurements

    Science.gov (United States)

    Tyralis, Hristos; Dimitriadis, Panayiotis; Koutsoyiannis, Demetris; O'Connell, Patrick Enda; Tzouka, Katerina; Iliopoulou, Theano

    2018-01-01

    The long-range dependence (LRD) is considered an inherent property of geophysical processes, whose presence increases uncertainty. Here we examine the spatial behaviour of LRD in precipitation by regressing the Hurst parameter estimate of mean annual precipitation instrumental data which span from 1916-2015 and cover a big area of the earth's surface on location characteristics of the instrumental data stations. Furthermore, we apply the Mann-Kendall test under the LRD assumption (MKt-LRD) to reassess the significance of observed trends. To summarize the results, the LRD is spatially clustered, it seems to depend mostly on the location of the stations, while the predictive value of the regression model is good. Thus when investigating for LRD properties we recommend that the local characteristics should be considered. The application of the MKt-LRD suggests that no significant monotonic trend appears in global precipitation, excluding the climate type D (snow) regions in which positive significant trends appear.

  6. Pacific Northwest Laboratory annual report for 1987 to the Assistant Secretary for Environment, Safety, and Health: Part 5: Environment, safety, health, and quality assurance

    International Nuclear Information System (INIS)

    Faust, L.G.; Steelman, B.L.; Selby, J.M.

    1988-02-01

    Part 5 of the 1987 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety, the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, and the Office of National Environmental Policy Act Project Assistance. For each project, as identified by the Field Work Proposal, articles describe progress made during fiscal year 1987. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work

  7. Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000

    International Nuclear Information System (INIS)

    2001-01-01

    This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction

  8. Annual report to Congress. Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 2000

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-03-01

    This Annual Report to the Congress describes the Department of Energy's activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board. During 2000, the Department completed its implementation and proposed closure of one Board recommendation and completed all implementation plan milestones associated with two additional Board recommendations. Also in 2000, the Department formally accepted two new Board recommendations and developed implementation plans in response to those recommendations. The Department also made significant progress with a number of broad-based safety initiatives. These include initial implementation of integrated safety management at field sites and within headquarters program offices, issuance of a nuclear safety rule, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

  9. Increasing NASA SSC Range Safety by Developing the Framework to Monitor Airspace and Enforce Restrictions

    Data.gov (United States)

    National Aeronautics and Space Administration — The NASA John C. Stennis Space Center (SSC) Office of Safety and Mission Assurance (SMA) has a safety concern associated with unauthorized aircraft entering...

  10. Enhancing swimming pool safety by the use of range-imaging cameras

    Science.gov (United States)

    Geerardyn, D.; Boulanger, S.; Kuijk, M.

    2015-05-01

    Drowning is the cause of death of 372.000 people, each year worldwide, according to the report of November 2014 of the World Health Organization.1 Currently, most swimming pools only use lifeguards to detect drowning people. In some modern swimming pools, camera-based detection systems are nowadays being integrated. However, these systems have to be mounted underwater, mostly as a replacement of the underwater lighting. In contrast, we are interested in range imaging cameras mounted on the ceiling of the swimming pool, allowing to distinguish swimmers at the surface from drowning people underwater, while keeping the large field-of-view and minimizing occlusions. However, we have to take into account that the water surface of a swimming pool is not a flat, but mostly rippled surface, and that the water is transparent for visible light, but less transparent for infrared or ultraviolet light. We investigated the use of different types of 3D cameras to detect objects underwater at different depths and with different amplitudes of surface perturbations. Specifically, we performed measurements with a commercial Time-of-Flight camera, a commercial structured-light depth camera and our own Time-of-Flight system. Our own system uses pulsed Time-of-Flight and emits light of 785 nm. The measured distances between the camera and the object are influenced through the perturbations on the water surface. Due to the timing of our Time-of-Flight camera, our system is theoretically able to minimize the influence of the reflections of a partially-reflecting surface. The combination of a post image-acquisition filter compensating for the perturbations and the use of a light source with shorter wavelengths to enlarge the depth range can improve the current commercial cameras. As a result, we can conclude that low-cost range imagers can increase swimming pool safety, by inserting a post-processing filter and the use of another light source.

  11. The Nirex safety assessment research programme: annual report for 1985/86

    International Nuclear Information System (INIS)

    Hodgkinson, D.P.; Cooper, M.J.; Atkinson, A.

    1987-01-01

    The report describes progress of the Nirex Safety Assessment Research Programme in 1985/86. In addition, some background information is given on the overall programme and on the individual research projects, and likely future work is outlined. Research into the disposal of low-level waste (LLW) and intermediate-level waste (ILW) into underground repositories and onto the sea bed is reported. A large part of the programme is concerned with the effectiveness of near-field barriers to water-borne leakage of radionuclides from cementitious repositories. Considerable progress has been made with quantifying the longevity of steel containers and concrete structures, and the effectiveness of chemical constraints in limiting near-field concentrations. A range of techniques for measuring and modelling far-field phenomena has been developed and tested. Some initial studies have been performed to assess the durability of sea disposal packages and the behaviour of polythene in sea water. (author)

  12. [Does annual simulation training influence the safety climate of a university hospital? : Prospective 5‑year investigation using dimensions of the safety attitude questionnaire].

    Science.gov (United States)

    St Pierre, M; Gall, C; Breuer, G; Schüttler, J

    2017-12-01

    Simulation-based training with a focus on non-technical skills can have a positive influence on safety relevant attitudes of participants. If an organization succeeds in training sufficient staff, it may experience a positive change in the safety climate. As the effects of a single training are of a transient nature, annual training sessions may lead to an incremental improvement of safety relevant attitudes of employees over time. In spring 2012 the Department of Anesthesia at the University Hospital of Erlangen established an annual simulation-based training for staff members (e.g. consultants, trainee anesthetists and nurse anesthetists). The study aimed to test whether an annual simulation-based training would result in an incremental longitudinal improvement in attitudes towards teamwork, safety and stress recognition. A survey comprising three domains (teamwork climate, safety climate and stress recognition) of the safety attitudes questionnaire (SAQ) and items addressing briefing and speaking up was distributed to all participants in an annual in-house simulation training. Participants filled out the questionnaire in the morning of each training day. The attitudes were measured before the first training series in 2012, 6 months after the first training and then every year (2013-2016). Participants generated a personalized identification code which allowed individuals to be anonymously tracked over time. Results of the 5‑point Likert scale were transformed to a 100-point scale. Results were calculated at the group level and at the individual level. Univariable linear regression was used to calculate mean changes per year. Over a period of 5 years (2012-2016) a total of 255 individuals completed the questionnaire. Each year, 14-20% of all nurse anesthetists and 81-90% of all anesthetists participated in the simulation-based training. As a result of annual staff turnover 16-24% of participants were new staff members. A personalized code allowed the

  13. Pacific Northwest Laboratory annual report for 1989 to the Assistant Secretary for Environment, Safety, and Health - Part 5: Environment, Safety, Health, and Quality Assurance

    Energy Technology Data Exchange (ETDEWEB)

    Faust, L.G.; Doctor, P.G.; Selby, J.M.

    1990-04-01

    Part 5 of the 1989 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, the Office of National Environmental Policy Act Project Assistance, the Office of Nuclear Safety, the Office of Safety Compliance, and the Office of Policy and Standards. For each project, as identified by the Field Work Proposal, there is an article describing progress made during fiscal year 1989. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work. 35 refs., 1 fig.

  14. 78 FR 26293 - Safety Zones; Annual Events in the Captain of the Port Detroit Zone

    Science.gov (United States)

    2013-05-06

    ... announced by a later notice in the Federal Register. B. Regulatory History and Information On August 8, 2008... be determined annually. (2) BGSU Football Gridiron Classic Golf and Dinner Fireworks, Catawba Island.... The exact dates and times will be determined annually. (61) BGSU Football Gridiron Classic Golf and...

  15. Proceedings of the twenty-fifth annual institute on mining health, safety and research

    Energy Technology Data Exchange (ETDEWEB)

    Tinney, G.R.; Bacho, A.; Karmis, M. [eds.

    1994-12-31

    The keynote session included papers on the US Bureau of Mines - a vision for the future; clean, green and lean; and the psychology of occupational safety. The technical sessions include panel discussions on Virginia`s revised mine safety regulations, and on independent contractors. Other papers covered: criminal enforcement of regulatory violations; accidents during surface mine mobile equipment; Federal Mine Safety and Health Review Commission; safety, technological and productivity potentials of highwall mining; and accidents caused by falls of unsupported roof.

  16. 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)

  17. 78 FR 20454 - Safety Zones; Annual Events Requiring Safety Zones in the Captain of the Port Lake Michigan Zone

    Science.gov (United States)

    2013-04-05

    ... Zone. The last three entries within this rule have been added for races in the Chicago, IL area and on... written--Celebrate Americafest/Fire over the Fox. This event has historically involved both a fireworks... day of the event. To ensure the safety of the Celebrate Americafest/Fire over the Fox event in its...

  18. 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

  19. Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-02-01

    This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted in the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.

  20. Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999

    International Nuclear Information System (INIS)

    2000-01-01

    This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted in the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction

  1. Industrial Safety and Applied Health Physics Division, annual report for 1982

    International Nuclear Information System (INIS)

    1983-12-01

    Activities during the past year are summarized for the Health Physics Department, the Environmental Management Department, and the Safety Department. The Health Physics Department conducts radiation and safety surveys, provides personnel monitoring services for both external and internal radiation, and procures, services, and calibrates appropriate portable and stationary health physics instruments. The Environmental Management Department insures that the activities of the various organizations within ORNL are carried out in a responsible and safe manner. This responsibility involves the measurement, field monitoring, and evaluation of the amounts of radionuclides and hazardous materials released to the environment and the control of hazardous materials used within ORNL. The department also collaborates in the design of ORNL Facilities to help reduce the level of materials released to the environment. The Safety Department is responsible for maintaining a high level of staff safety. This includes aspects of both operational and industrial safety and also coordinates the activities of the Director's Safety Review Committee

  2. Industrial Safety and Applied Health Physics Division, annual report for 1982

    Energy Technology Data Exchange (ETDEWEB)

    1983-12-01

    Activities during the past year are summarized for the Health Physics Department, the Environmental Management Department, and the Safety Department. The Health Physics Department conducts radiation and safety surveys, provides personnel monitoring services for both external and internal radiation, and procures, services, and calibrates appropriate portable and stationary health physics instruments. The Environmental Management Department insures that the activities of the various organizations within ORNL are carried out in a responsible and safe manner. This responsibility involves the measurement, field monitoring, and evaluation of the amounts of radionuclides and hazardous materials released to the environment and the control of hazardous materials used within ORNL. The department also collaborates in the design of ORNL Facilities to help reduce the level of materials released to the environment. The Safety Department is responsible for maintaining a high level of staff safety. This includes aspects of both operational and industrial safety and also coordinates the activities of the Director's Safety Review Committee. (ACR)

  3. Annual activity report of Ignalina NPP Safety Analysis Group for 1996 year

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.

    1997-03-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1996 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. Ignalina Safety Analysis Report was prepared on the basis of these results. 37 refs., 9 tabs., 96 figs

  4. Annual report on the administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, (1988), April 1, 1989. Annual report

    International Nuclear Information System (INIS)

    1989-01-01

    The Secretary of Health and Human Services is required by Subpart 3, Part F of Title III of the Public Health Service Act; 42 USC 263b et seq. (Public Law 90-602) to submit an annual report to the President for transmittal to the Congress on or before April 1 on the administration of the Radiation Control for Health and Safety Act. The detailed information required in the report is outlined in Section 360D of the Public Health Service Act. The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1988. In reviewing the operations of the Center for Devices and Radiological Health as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report)

  5. KIT safety management. Annual report 2012; KIT-Sicherheitsmanagement. Jahresbericht 2012

    Energy Technology Data Exchange (ETDEWEB)

    Frank, Gerhard (ed.)

    2013-07-01

    The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

  6. 2016 Annual Site Environmental report Sandia National Laboratories Tonopah Test Range Nevada & Kaua'i Test Facility Hawai'i.

    Energy Technology Data Exchange (ETDEWEB)

    Salas, Angela Maria [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Griffith, Stacy R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-07-01

    Sandia National Laboratories (SNL) is a multimission laboratory managed and operated by National Technology & Engineering Solutions of Sandia, LLC, a wholly owned subsidiary of Honeywell International Inc., for the U.S. Department of Energy’s (DOE’s), National Nuclear Security Administration (NNSA) under contract DE-NA0003525. The DOE/NNSA Sandia Field Office administers the contract and oversees contractor operations at the SNL, Tonopah Test Range (SNL/TTR) in Nevada and the SNL, Kaua‘i Test Facility (SNL/KTF) in Hawai‘i. SNL personnel manage and conduct operations at SNL/TTR in support of the DOE/NNSA’s Weapons Ordnance Program and have operated the site since 1957. Navarro Research and Engineering personnel perform most of the environmental programs activities at SNL/TTR. The DOE/NNSA/Nevada Field Office retains responsibility for cleanup and management of SNL/TTR Environmental Restoration sites. SNL personnel operate SNL/KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of sustainability, environmental protection, and monitoring programs at SNL/TTR and SNL/KTF during calendar year 2016. Major environmental programs include air quality, water quality, groundwater protection, terrestrial and biological surveillance, waste management, pollution prevention, environmental restoration, oil and chemical spill prevention, and implementation of the National Environmental Policy Act. This ASER is prepared in accordance with and as required by DOE O 231.1B, Admin Change 1, Environment, Safety, and Health Reporting.

  7. 78 FR 11798 - Safety Zones; Annual Fireworks Events in the Captain of the Port Buffalo Zone

    Science.gov (United States)

    2013-02-20

    ... later notice in the Federal Register. B. Regulatory History and Information On June 18, 2008, the Coast... coordinates for the safety zones corresponding with the Browns Football Half time Fireworks and the Lorain... Football Half time and the Lorain Port Fest safety zones, to include changing the format of the coordinates...

  8. Annual activity report of Ignalina NPP Safety Analysis Group for 1995 year

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.

    1995-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1995 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. 18 refs., 9 tabs., 110 figs

  9. Annual activity report of Ignalina NPP Safety Analysis Group for the year 1997

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.; Kaliatka, A

    1998-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for the year 1997 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system

  10. 33 CFR 165.1406 - Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii.

    Science.gov (United States)

    2010-07-01

    ... Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and...), Barking Sands, Island of Kauai, Hawaii. (a) Location. The following area is established as a safety zone during launch operations at PMRF, Kauai, Hawaii: The waters bounded by the following coordinates: (22°01...

  11. 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.

  12. Fusion-Reactor-Safety Research Program. Annual report, Fiscal Year 1981

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1982-07-01

    The report contains four sections: Outside Contracts includes the continuation of the General Atomic Co. low-activation materials safety study, water-cooled transport activation products study by Pacific Northwest Laboratory (PNL), studies of superconducting magnet safety conducted by Argonne National Laboratory (ANL) coupled with a new experimental superconducting magnet study program by Massachusetts Institute of Technology (MIT) to verify analytical work, a continuation of safety methodology work by MIT, portions of papers on lithium safety studies conducted at Hanford Engineering Development Laboratory (HEDL), and a new program to study tritium gas conversion to tritiated water at Oak Ridge National Laboratory (ORNL). The section EG and G idaho, Inc., Activities at INEL includes adaptations of papers of ongoing work in transient code development, tritium systems risk assessment, heat transfer activities, and a summary of a workshop on safety in design. A List of Publications and Proposed FY-82 Activities are also presented

  13. 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.

  14. Status of safety in nuclear facilities - 2012. AREVA General Inspectorate Annual report

    International Nuclear Information System (INIS)

    2013-05-01

    After a message from the Areva's Chief Executive Officer and a message from the senior Vice President of safety, health, security, sustainable development, a text by the inspector general comments the key safety results (events, dose levels, radiological impacts), the inspection findings, the areas of vigilance (relationship with the ASN, the management of the criticality risk, and facility compliance), some significant topics after the Fukushima accident. Then this report addresses the status of nuclear safety and radiation protection in the group's facilities and operations. It more specifically addresses the context and findings (lessons learned from the inspections, operating experience from event, employee radiation monitoring, environmental monitoring), crosscutting processes (safety management, controlling facility compliance, subcontractor guidance and management, crisis management), specific risks (criticality risk, fire hazards, transportation safety, radioactive waste management, pollution prevention, liability mitigation and dismantling), and areas for improvement and outlook

  15. Aspects of safety and reliability for fusion magnet systems first annual report

    International Nuclear Information System (INIS)

    Powell, J.

    1976-01-01

    General systems aspects of fusion magnet safety are examined first, followed by specific detailed analyses covering structural, thermal, electrical, and other aspects of fusion magnet safety. The design examples chosen for analysis are illustrative and are not intended to be definitive, since fusion magnet designs are rapidly evolving. Included is a comprehensive collection of design and operating data relating to the safety of existing superconducting magnet systems. The remainder of the overview lists the main conclusions developed from the work to date. These should be regarded as initial steps. Since this study has concentrated on examining potential safety concerns, it may tend to overemphasize the problems of fusion magnets. In fact, many aspects of fusion magnets are well developed and are consistent with good safety practice. A short summary of the findings of this study is given

  16. KIT safety management. Annual report 2013; KIT-Sicherheitsmanagement. Jahresbericht 2013

    Energy Technology Data Exchange (ETDEWEB)

    Frank, Gerhard (ed.)

    2014-07-01

    The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for licensing procedures, industrial safety organization, control of environmental protection measures, planning and implementation of emergency preparedness and response, operation of radiological laboratories and measurement stations, extensive radiation protection support and the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2013. Status figures in principle reflect the status at the end of the year 2013. The processes described cover the areas of competence of KSM. Due to changes in the organization of the infrastructural service units in KIT, KSM has been cancelled at the end of 2013. Its tasks will mainly be covered in 2014 by the new founded service unit Safety and Environmental (Sicherheit und Umwelt, SUM). The departments Campus Security, Fire Brigade and Information Technology have been transferred to the Service Unit General Services (Allgemeine Services, ASERV).

  17. 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.

  18. 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.

  19. 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

  20. Annual report 1985 of the KfK Central Safety Department

    International Nuclear Information System (INIS)

    Kiefer, H.; Koelzer, W.; Koenig, L.A.

    1986-04-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1985 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

  1. 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

  2. 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

  3. 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

  4. 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.

  5. 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

  6. The Nirex safety assessment research programme: annual report for 1986/87

    International Nuclear Information System (INIS)

    Cooper, M.J.; Hodgkinson, D.P.

    1987-05-01

    This report describes research relating to the underground disposal of low-level and intermediate-level radioactive wastes, to provide information for post-emplacement radiological safety assessment. Topics reported are solubility and sorption, organic degradation, microbial activity, leaching, the corrosion of containers, and radionuclide migration studies. Properties of clays, slates, colloids and uranium disequilibrium are studied. Mathematical modelling to support the safety assessment of radioactive waste disposal is also studied. (U.K.)

  7. AREVA General Inspectorate 2010 Annual Report. Status of safety in nuclear facilities

    International Nuclear Information System (INIS)

    2010-01-01

    After messages by different managers, this report proposes a description of the context for nuclear safety: group's policy in matters of nuclear safety and radiation protection, regulatory changes (in France, with respect to information, changes in administrative organization, overhaul of general technical regulations, international context). It describes the organizational changes which occurred within the company. It reports actions regarding transparency, briefly describes actions and principles aimed at improving safety, indicates and comments noteworthy nuclear events, discusses their assessment from a HOF (human and organizational factors) perspective, comments lessons learned from inspections, comments data regarding radiation protection and actions aimed at improving radiation protection. It discusses environmental impact issues. It addresses the different processes and factors which transversely appear in nuclear safety: safety management, human and organizational factors, safety in design, project management, and emergency management. Several specific risks are discussed: criticality control, nuclear materials safeguards, fire, spill prevention, transportation, radioactive waste, shutdown and dismantling, service operations, mining, and environmental liabilities. Document in French and in English

  8. Paul Scherrer Institut annual report 1996. Annex IV: PSI nuclear energy and safety research

    International Nuclear Information System (INIS)

    Birchley, J.; Roesel, R.; Wellner, A.

    1997-01-01

    The department 'Nuclear Energy and Safety Research' (F4) at PSI carries the responsibility of performing the essential nuclear energy research in Switzerland. This research is part of the remit of PSI and follows government directive; about one-fifth of the Institute's Federal budget is allocated to this task. Currently about 190 persons are working in this field. Approximately 45% of the salary and investment costs (5.5 million CHF in the budget period 1996/97) are externally funded. This funding is provided primarily by the Swiss Utilities, the NAGRA and the safety authority HSK. The activities in nuclear research concentrate on three main domains: safety and safety related problems of operating plants, safety features of future reactor and fuel cycle concepts and waste management; another 4% of staff are addressing broader aspects of energy. At the end of 1996, a policy evaluation with the laboratory heads took place in order to redefine the direction of F4 activities. (author) figs., tabs., refs

  9. Guide for preparing annual reports on radiation-safety testing of electronic products (general)

    International Nuclear Information System (INIS)

    1987-10-01

    For manufacturers of electronic products other than those for which a specific guide has been issued, the guide replaces the Guide for the Filing of Annual Reports (21 CFR Subchapter J, Section 1002.11), HHS Publication FDA 82-8127. The electronic product (general) annual reporting guide is applicable to the following products: products intended to produce x radiation (accelerators, analytical devices, therapy x-ray machines); microwave diathermy machines; cold-cathode discharge tubes; and vacuum switches and tubes operating at or above 15,000 volts. To carry out its responsibilities under Public Law 90-602, the Food and Drug Administration's Center for Devices and Radiological Health (CDRH) has issued a series of regulations contained in Title 21 of the Code of Federal Regulations (CFR). Part 1002 of 21 CFR deals with records and reports. Section 1002.61 categorizes electronic products into Groups A through C. Section 1002.30 requires manufacturers of products in Groups B and C to establish and maintain certain records, while Section 1002.11 requires such manufacturers to submit an Annual Report summarizing the contents of the required records. Section 1002.7 requires that reports conform to reporting guides issued by CDRH unless an acceptable justification for an alternate format is provided

  10. Paul Scherrer Institut annual report 1995. Annex IV: PSI nuclear energy and safety

    Energy Technology Data Exchange (ETDEWEB)

    Birchley, J.; Roesel, R.; Doesburg, R. van [eds.] [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-09-01

    Nuclear energy research in Switzerland is concentrated at PSI`s Department F4. It is explicitly mentioned in the Institute`s official charter and commands about one fifth of the Institute`s federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI`s activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs.

  11. Annual report 1995 of the Central Safety Department, Research Center Karlsruhe

    International Nuclear Information System (INIS)

    Koelzer, W.

    1996-04-01

    The Central Safety Department is responsible for supervising, monitoring and, to some extent, also executing measures of radiation protection, industrial health and safety as well as physical protection and security at and for the institutes and departments of the Karlsruhe Research Center (Forschungszentrum Karlsruhe GmbH), and for monitoring liquid effluents and the environment of all facilities and nuclear installations on the premises of the Research Center. In addition, research and development work is carried out in the fields of behavior of tritium in the air/soil/plant system, tritium balances for nuclear fusion fuel cycles, and assessments of mining and ore dressing spoils. This report gives details of the different duties and reports the results of 1995 routine tasks, investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  12. Paul Scherrer Institut annual report 1995. Annex IV: PSI nuclear energy and safety

    International Nuclear Information System (INIS)

    Birchley, J.; Roesel, R.; Doesburg, R. van

    1996-01-01

    Nuclear energy research in Switzerland is concentrated at PSI's Department F4. It is explicitly mentioned in the Institute's official charter and commands about one fifth of the Institute's federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI's activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs

  13. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L. [eds.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

  14. Annual report 2005 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Stritar, A.; Kostadinov, V.

    2006-06-01

    The year 2005 was without major problems in the area of protection against ionizing radiation and nuclear safety in Slovenia. There were no events that would present radiological threat to the population. This report contains the essential data on the status in the areas of radiation protection and nuclear safety in the country, and is aimed at a wider group of interested public. At the same time the extended version is prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on a CD-ROM or at the home page of the SNSA. (author)

  15. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 5 tabs., 21 ills

  16. Annual report 2006 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Stritar, A.; Kostadinov, V.

    2007-05-01

    In the year 2006 there were no major problems in the area of protection against ionizing radiation and nuclear safety in Slovenia. There were no events that would present a radiological threat to the population. This report contains the essential data on the status in the areas of radiation protection and nuclear safety in the country, and is aimed at a wider group of interested public. At the same time an extended version is prepared consisting of all details and data which would be of interest to a narrower group of professionals. It is available in electronic form on CD-ROM and on the homepage of the SNSA. (author)

  17. The Nirex Safety Assessment Research Programme; annual report for 1988/89

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1989-07-01

    This report summarises progress of the Nirex Safety Assessment Research Programme during 1988/89, in support of assessments of the post-emplacement radiological safety of a repository for the disposal of low-level and intermediate-level radioactive waste. During this period the assessments were concentrating on a comparative study of concepts and areas for deep emplacement of waste, in order to assist in the selection of preferred sites, and the research programme was therefore focussed on providing the data necessary for broad comparisons between different options to be made. (author)

  18. Annual report 2006 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Stritar, A.; Kostadinov, V.

    2007-05-01

    In the year 2006 there were no major problems in the area of protection against ionizing radiation and nuclear safety in Slovenia. There were no events that would present a radiological threat to the population. This report contains the essential data on the status in the areas of radiation protection and nuclear safety in the country, and is aimed at a wider group of interested public. At the same time an extended version is prepared consisting of all details and data which would be of interest to a narrower group of professionals. It is available in electronic form on CD-ROM and on the homepage of the SNSA.

  19. DOE Safety Metrics Indicator Program (SMIP) Fiscal Year 2000 Annual Report of Packaging- and Transportation-related Occurrences

    International Nuclear Information System (INIS)

    Dickerson, L.S.

    2001-01-01

    The U.S. Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS) is an interactive computer system designed to support DOE-owned or -operated facilities in reporting and processing information concerning occurrences related to facility operations. The Oak Ridge National Laboratory has been charged by the DOE National Transportation Program Albuquerque (NTPA) with the responsibility of retrieving reports and information pertaining to packaging and transportation (P and T) incidents from the centralized ORPS database. These selected reports are analyzed for safety concerns, trends, potential impact on P and T operations, and ''lessons learned'' in P and T safety. To support this analysis and trending, the Safety Metrics Indicator Program (SMIP) was established by the NTPA in fiscal year (FY) 1998. Its chief goal is to augment historical reporting of occurrence-based information by providing (1) management notification of those incidents that require attention, (2) an accurate picture of contractors' P and T-related performance, and (3) meaningful statistics on occurrences at particular sites, including comparisons among different contractor sites and between DOE and the private sector. This annual report contains information on those P and T-related occurrences reported to the ORPS during the period from October 1, 1999, through September 30, 2000. Only those incidents that occur in preparation for transport, during transport, and during unloading of hazardous material are considered as packaging- or transportation-related occurrences

  20. Challenges in the Acceptance/Licensing of a Mobile Ballistic Missile Range Safety Technology (BMRST) System

    National Research Council Canada - National Science Library

    Bartone, Chris

    2001-01-01

    ...), Space Vehicle Directorate, Ballistic Missile Technology program. The BMRST Program is to develop and to demonstrate a "certifiable" mobile launch range tracking and control system based upon the Global Positioning System (GPS...

  1. Nuclear Research Centre Juelich. 1986 annual work report of the Department for Safety and Radiation Protection

    International Nuclear Information System (INIS)

    Hille, R.; Frenkler, K.L.

    1986-02-01

    The Department for Safety and Radiation Protection continues to be responsible for coordinating radiation protection, safety and protection at the KFA. It supports the other institutes and departments in performing the safety tasks allotted to them. The principal tasks of the Department are in administrative and technical assistance to these organization units and in safeguards. Administrative assistance involves, for example, regulation of the radiation protection organization in the institutes, including the appointment of radiation protection officers (Strahlenschutzbeauftragte). Furthermore, this includes the central handling of the registration system with the authorities and dealing with outside firms thus considerably relieving the institutes of their administrative tasks. Handling licensing procedures and the central accountancy of radioactive materials is also to be mentioned in this context. Technical assistance largely consists of developing, maintaining and repairing radiation measuring instruments and in the monitoring of personnel by evaluating personnel dosimeters and incorporation controls for radioactive sources. The safeguards tasks of the Department concern the very staff-intensive physical protection, as well as environmental protection and industrial safety. (orig./HP) [de

  2. 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

  3. Nuclear Research Centre Juelich. 1987 annual work report of the Department for Safety and Radiation Protection

    International Nuclear Information System (INIS)

    Hille, R.

    1988-03-01

    The Department for Safety and Radiation Protection continues to be responsible for coordinating radiation protection, safety and protection at the KFA. It supports the other institutes and departments in performing the safety tasks allotted to them. The principal tasks of the Department are in administrative and technical assistance to these organization units and in safeguards. Administrative assistance involves, for example, regulation of the radiation protection organization in the institutes, including the appointment of radiation protection officers (Strahlenschutzbeauftragte). Furthermore, this includes the central handling of the registration system with the authorities and dealing with outside firms thus considerably relieving the institutes of their administrative tasks. Handling licensing procedures and the central accountancy of radioactive materials is also to be mentioned in this context. Technical assistance largely consists of developing, maintaining and repairing radiation measuring instruments and in the monitoring of personnel by evaluating personnel dosimeters and incorporation controls for radioactive sources. The safeguards tasks of the Department concern the very staff-intensive physical protection, as well as environmental protection and industrial safety. (orig./HP) [de

  4. 77 FR 38484 - Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone

    Science.gov (United States)

    2012-06-28

    ... zone will be enforced from 10:00 p.m. to 11:00 p.m. on July 5, 2012. (8) Grosse Isle Yacht Club.... (16) Grosse Pointe Yacht Club 4th of July Fireworks, Grosse Pointe Shores, MI. The safety zone listed...

  5. 78 FR 40961 - Safety Zones; Annual Events in the Captain of the Port Detroit Zone

    Science.gov (United States)

    2013-07-09

    ...(a)(19) will be enforced from 10:30 p.m. to 10:30 p.m. on July 3, 2013. (22) Grosse Ile Yacht Club..., 2013. (24) Grosse Pointe Yacht Club 4th of July Fireworks, Grosse Pointe Shores, MI. The safety zone...

  6. 1988 annual work report of the Department for Safety and Radiation Protection

    International Nuclear Information System (INIS)

    Hille, R.

    1989-03-01

    The Department for Safety and Radiation Protection continues to be responsible for coordinating radiation protection, safety and protection at the KFA. It supports the other institutes and departments in performing the safety tasks allotted to them. The principal tasks of the Department are in administrative and technical assistance to these organization units and in safeguards. Administrative assistance involves, for example, regulation of the radiation protection organization in the institutes, including the appointment of radiation protection officers (Strahlenschutzbeauftragte). Furthermore, this includes the central handling of the registration system with the authorities and dealing with outside firms thus considerably relieving the institutes of their administrative tasks. Handling licensing procedures and the central accountancy of radioactive materials is also to be mentioned in this context. Technical assistance largely consists of developing, maintaining and repairing radiation measuring instruments and in the monitoring of personnel by evaluating personnel dosimeters and incorporation controls for radioactive sources. The safeguards tasks of the Department concern the very staff-intensive physical protection, as well as environmental protection and industrial safety. (orig.) [de

  7. 1989 annual work report of the KFA Department for Safety and Radiation Protection

    International Nuclear Information System (INIS)

    Hille, R.; Frenkler, K.L.

    1990-03-01

    The Department for Safety and Radiation Protection continues to be responsible for coordinating radiation protection, safety and protection at the KFA. It supports the other institutes and departments in performing the safety tasks allotted to them. The principal tasks of the Department are in administrative and technical assistance to these organization units and in safeguards. Administrative assistance involves, for example, regulation of the radiation protection organization in the institutes, including the appointment of radiation protection officers (Strahlenschutzbeauftrage). Furthermore, this includes the central handling of the registration system with the authorities and dealing with outside firms thus considerably relieving the institutes of their administrative tasks. Handling licensing procedures and the central accountancy of radioactive materials is also to be mentioned in this context. Technical assistance largely consists of developing, maintaining and repairing radiation measuring instruments and in the monitoring of personnel by evaluating personnel dosimeters and incorporation controls for radioactive sources. The safeguards tasks of the Department concern the very staff-intensive physical protection, as well as environmental protection and industrial safety. (orig.) [de

  8. 78 FR 23850 - Safety Zones; Annual Fireworks Events in the Captain of the Port Buffalo Zone

    Science.gov (United States)

    2013-04-23

    .... Regulatory History and Information On June 18, 2008, the Coast Guard put 33 CFR 165.939 into effect, which... Football Half time Fireworks and the Lorain Port Fest Fireworks are formatted differently than the other... zones. Likewise, this rule will amend the Browns Football Half time and the Lorain Port Fest safety...

  9. Annual activity report of Ignalina NPP Safety Analysis Group for 1994 year

    International Nuclear Information System (INIS)

    Ushpuras, E.; Kaliatka, A.; Chesna, B.; Dundulis, G.

    1995-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1994 are presented. ISAG is concentrated its research activities into 3 areas: the neutrons dynamics modeling, simulation of transient processes during loss of coolant accident and calculation of reactor building structure's streses and other mechanical properties in the case of accident. 6 refs., 13 tabs., 69 figs

  10. Annual progress report FY 1977. [Computer calculations of light water reactor dynamics and safety

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, K.F.; Henry, A.F.

    1977-07-01

    Progress is summarized in a project directed toward development of numerical methods suitable for the computer solution of problems in reactor dynamics and safety. Specific areas of research include methods of integration of the time-dependent diffusion equations by finite difference and finite element methods; representation of reactor properties by various homogenization procedures; application of synthesis methods; and development of response matrix techniques.

  11. Proceedings of the Annual Major Range and Test Facility Base (MRTFB) environmental Workshop (4th) Held in Alexandria, Virginia on 26-28 April 1994

    Science.gov (United States)

    1994-07-01

    Copy 0of 37 Copts$ | AD-A285 779 SIDA DOCUMENT D- 1537 I PROCEEDLNGS OF THE FOURTH ANNUAL MAJOR RANGE AND TEST FACILITY BASE (MRTFB...DEFENSE ANALYSES 񓜩 N. Beauregard Street, Alexandria, Virginia 22311-1772 SIDA Log No. HU 94-45640 * III i DEFINITIONS IDA publishes the follewing...woodpecker. The RCW is a good indicator of ecosystem health in VIH -36 I I the longleaf pine ecosystem. This survey identified Eglin as having the fourth

  12. System and safety studies of accelerator driven transmutation. Annual Report 2001

    International Nuclear Information System (INIS)

    Gudowski, W.; Wallenius, J.; Tucek, K.; Eriksson, Marcus; Carlsson, Johan; Seltborg, P.; Cetnar, J.; Chakarova, R.; Westlen, D.

    2002-03-01

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the Dept. of Nuclear and Reactor Physics has been focused in year 2001 on: a) ADS core design and development of advanced nuclear fuel optimised for high transmutation rates and good safety features; b) analysis of ADS-dynamics; c) computer code and nuclear data development relevant for simulation and optimization of ADS; d) participation in ADS experiments including 1 MW spallation target manufacturing, subcritical experiments MUSE (CEA-Cadarache) and YALINA experiment in Minsk. The Dept. is very actively participating in many European projects in the 5th Framework Programme of the European Community. Most of the research topics reported in this paper are referred to by appendices, which have been published in the open literature. The topics, which are not yet published, are described here in more details

  13. System and safety studies of accelerator driven transmutation. Annual Report 2001

    Energy Technology Data Exchange (ETDEWEB)

    Gudowski, W; Wallenius, J; Tucek, K; Eriksson, Marcus; Carlsson, Johan; Seltborg, P; Cetnar, J; Chakarova, R; Westlen, D [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    2002-03-01

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the Dept. of Nuclear and Reactor Physics has been focused in year 2001 on: a) ADS core design and development of advanced nuclear fuel optimised for high transmutation rates and good safety features; b) analysis of ADS-dynamics; c) computer code and nuclear data development relevant for simulation and optimization of ADS; d) participation in ADS experiments including 1 MW spallation target manufacturing, subcritical experiments MUSE (CEA-Cadarache) and YALINA experiment in Minsk. The Dept. is very actively participating in many European projects in the 5th Framework Programme of the European Community. Most of the research topics reported in this paper are referred to by appendices, which have been published in the open literature. The topics, which are not yet published, are described here in more details.

  14. 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)

  15. Nirex safety assessment research programme: annual report for 1985/86

    International Nuclear Information System (INIS)

    Hodgkinson, D.P.; Cooper, M.J.

    1987-01-01

    The purpose of this report is to provide information for post-emplacement radiological safety assessment relating to the disposal of intermediate-level and low-level radioactive wastes into underground repositories and the sea bed. Topics reported are chemical equilibrium studies, laser spectroscopy, the corrosion of containers, properties of concretes, microbiology, transport in clays, the behaviour of sea disposal packages and leaching from cements in seawater. There is close contact between experimental work and mathematical modelling. (U.K.)

  16. Pacific Northwest Laboratory annual report for 1980 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health and safety

    International Nuclear Information System (INIS)

    Baalman, R.W.; Hays, I.D.

    1981-02-01

    Pacific Northwest Laboratory's (PNL) 1980 annual report to the DOE Assistant Secretary for Environment describes research in environment, health, and safety conducted during fiscal year 1980. Part 5 includes technology assessments for natural gas, enhanced oil recovery, oil shale, uranium mining, magnetic fusion energy, solar energy, uranium enrichment and industrial energy utilization; regional analysis studies of environmental transport and community impacts; environmental and safety engineering for LNG, oil spills, LPG, shale oil waste waters, geothermal liquid waste disposal, compressed air energy storage, and nuclear/fusion fuel cycles; operational and environmental safety studies of decommissioning, environmental monitoring, personnel dosimetry, and analysis of criticality safety; health physics studies; and epidemiological studies. Also included are an author index, organization of PNL charts and distribution lists of the annual report, along with lists of presentations and publications

  17. Pacific Northwest Laboratory annual report for 1980 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health and safety

    Energy Technology Data Exchange (ETDEWEB)

    Baalman, R.W.; Hays, I.D. (eds.)

    1981-02-01

    Pacific Northwest Laboratory's (PNL) 1980 annual report to the DOE Assistant Secretary for Environment describes research in environment, health, and safety conducted during fiscal year 1980. Part 5 includes technology assessments for natural gas, enhanced oil recovery, oil shale, uranium mining, magnetic fusion energy, solar energy, uranium enrichment and industrial energy utilization; regional analysis studies of environmental transport and community impacts; environmental and safety engineering for LNG, oil spills, LPG, shale oil waste waters, geothermal liquid waste disposal, compressed air energy storage, and nuclear/fusion fuel cycles; operational and environmental safety studies of decommissioning, environmental monitoring, personnel dosimetry, and analysis of criticality safety; health physics studies; and epidemiological studies. Also included are an author index, organization of PNL charts and distribution lists of the annual report, along with lists of presentations and publications. (DLS)

  18. Pacific Northwest Laboratory annual report for 1983 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. Part 5. Overview and assessment

    International Nuclear Information System (INIS)

    Bair, W.J.

    1984-02-01

    The 1983 annual report from Pacific Northwest Laboratory (PNL) to the Department of Energy (DOE) describes research in environment, health, and safety conducted during fiscal year 1983. The report again consists of five parts, each in a separate volume. Part 5 of the 1983 Annual Report to the Department of Energy's Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety and the Office of Operational Safety. For each project, as identified by the Field Task Proposal/Agreement, articles describe progress made during FY 1983. Authors of these articles represent a broad spectrum of capabilities derived from various segments of the Laboratory, reflecting the interdisciplinary nature of the work

  19. Annual report 1999. NKS-programme 1998-2001[Nordic Nuclear Safety Programme]; Aarsrapport 1999. NKS-programmet 1998-2001

    Energy Technology Data Exchange (ETDEWEB)

    Bennerstedt, T. [ed.

    2000-02-01

    The Nordic nuclear safety programme consists of projects within the areas of risk assessment, reactor safety, waste, emergency preparedness, and environmental consequences. The annual report presents results and economic issues in relation to approved project plans and budgets. Also the more important reports, agreements, seminars, meetings etc are listed. Participating organisations and persons are mentioned, and the total national contributions (besides NKS- own means) to research are stated. (EHS)

  20. Annual Report 2003 on the Radiation and Nuclear Safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Kostadinov, V.; Stritar, A.

    2004-07-01

    This report is a continuation of a practice which was introduced a year ago. This short report provides in a condensed form the essential data on the situation in the country in the areas of radiation protection and nuclear safety, and is aimed at a wider group of interested public. In parallel, an extended report was prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on CD or at the home page of the SNSA.

  1. Annual report 2004 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Stritar, A.; Kostadinov, V.

    2005-06-01

    This short report is a continuation of the practice introduced two years ago. It provides in a condensed form the essential data on the status in the areas of radiation protection and nuclear safety in the country, and is aimed at a wider group of interested public. In parallel, an extended report was prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on a CD-ROM or at the home page of the SNSA. (author)

  2. Annual report 2003 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Kostadinov, V.; Stritar, A.

    2004-07-01

    This report is a continuation of a practice which was introduced a year ago. This short report provides in a condensed form the essential data on the situation in the country in the areas of radiation protection and nuclear safety, and is aimed at a wider group of interested public. In parallel, an extended report was prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on CD or at the home page of the SNSA. (author)

  3. Annual report 2004 on the radiation and nuclear safety in the Republic of Slovenia

    International Nuclear Information System (INIS)

    Stritar, A.; Kostadinov, V.

    2005-06-01

    This short report is a continuation of the practice introduced two years ago. It provides in a condensed form the essential data on the status in the areas of radiation protection and nuclear safety in the country, and is aimed at a wider group of interested public. In parallel, an extended report was prepared consisting of all the details and data which would be of interest to a narrower group of professionals. It is available in electronic form on a CD-ROM or at the home page of the SNSA.

  4. Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994; Forschungszentrum Karlsruhe, Projekt Nukleare Sicherheitsforschung. Jahrsbericht 1994

    Energy Technology Data Exchange (ETDEWEB)

    Hueper, R. [ed.

    1995-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [Deutsch] Seit Beginn 1990 sind die F+E-Arbeiten des Forschungszentrum Karlsruhe (FZKA) zur Reaktorsicherheit im Projekt Nukleare Sicherheitsforschung (PSF) zusammengefasst. Der vorliegende Jahresbericht 1994 enthaelt Beitraege zu aktuellen Fragen der Sicherheit von Leichtwasserreaktoren und innovativen Systemen sowie der Umwandlung von minoren Aktiniden. Die konkreten Forschungsthemen und -vorhaben werden mit internen und externen Fachgremien laufend abgestimmt. An den beschriebenen Arbeiten sind die folgenden Institute und Abteilungen des FZKA beteiligt: Institut fuer Materialforschung IMF I, II, III; Institut fuer Neutronenphysik und Reaktortechnik INR; Institut fuer Angewandte Thermo- und Fluiddynamik IATF; Institut fuer Reaktorsicherheit IRS; Hauptabteilung Ingenieurtechnik HIT; Hauptabteilung Versuchstechnik HVT sowie vom KfK beauftragte externe Institutionen. Die einzelnen Beitraege stellen den Stand der Arbeiten zum Fruehjahr 1995 dar und sind entsprechend dem F+E-Programm 1994 numeriert. Den in deutscher Sprache verfassten Beitraege sind Kurzfassungen in englischer Sprache vorangestellt. (orig.)

  5. System and safety studies of accelerator driven transmutation Annual Report 2005

    Energy Technology Data Exchange (ETDEWEB)

    Gudowski, Waclaw; Wallenius, Jan; Arzhanov, Vasily; Jolkkonen, Mikael; Eriksson, Marcus; Seltborg, Per; Westlen, Daniel; Lagerstedt, Christina; Isaksson, Patrick; Persson, Carl-Magnus; Aalander, Alexandra [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    2006-11-15

    The results of the research activities on System and Safety of Accelerator-Driven Transmutation (ADS) at the Department of Nuclear and Reactor Physics are described in this report followed by the Appendices of the relevant scientific papers published in 2005. PhD and Licentiate dissertations of Marcus Ericsson, Per Seltborg, Christina Lagerstedt and Daniel Westlen (see Appendices) reflect the research mainstream of 2005. Year 2005 was also very rich in international activities with ADS in focus. Summary of conferences, seminars and lecturing activities is given in Chapter 9 Research activities of 2005 have been focused on several areas: system and safety studies of ADS; subcritical experiments; ADS source efficiency studies; nuclear fuel cycle analysis; potential of reactor based transmutation; ADS fuel development; simulation of radiation damage; and development of codes and methods. Large part of the research activities has been well integrated with the European projects of the 5th and 6th Framework Programmes of the European Commission in which KTH is actively participating. In particular European projects: RED-IMPACT, CONFIRM, FUTURE, EUROTRANS and NURESIM.

  6. High committee for nuclear safety transparency and information. Annual activity report. June 2008 - December 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This document is the first activity report of the High committee for nuclear safety transparency and information (HCTISN), created on June 18, 2008. The HCTISN is a French authority of information, dialogue and debate about the risks linked with nuclear activities and about their impacts on public health, on the environment and on nuclear safety. The committee has the ability to express his opinion and recommendations about any question on the above topics and to propose any measure aiming at warranting or improving the transparency in the nuclear domain. This activity report offers a synthetic overview of the actions already undertaken: the plutonium imports from UK, the contamination incident at the Socatri facility (a Areva-Eurodif daughter company located at the Tricastin site), and the dismantling strategy of basic nuclear facilities. It presents the composition, organization, missions and means of the Committee, the different working groups and the follow-up of the different recommendations emitted so far by the Committee. (J.S.)

  7. Manche storage Centre. Information report on nuclear safety and radiation protection 2014. Annual report 2014

    International Nuclear Information System (INIS)

    2015-06-01

    After a presentation of the Manche Storage Centre (CSM), the first French centre of surface storage of weakly and moderately radioactive wastes, of its history, its buildings and activities, of the multi-layer cover, of the water management system (installation, controls, sampling), this report then describes the measures related to nuclear safety (principles and objectives), the management of conventional and nuclear wastes produced by the Centre and its other environmental impacts. The follow up of the installations and of their effluents and releases are then addressed: origin, locations and results of radiological controls of rainfalls, of risky effluents, of underground waters, of rivers, impacts of the Centre on its environment (releases in the sea, in rivers, in sediments). The measures related to radiation protection are described: principles, staff dosimetry, and personnel safety. The next part presents the nuclear event scale (INES) and indicates that no incident occurred in 2014. Finally the actions related to public information and transparency are summarized. Recommendations of the CHSCT are reported at the end

  8. System and safety studies of accelerator driven transmutation. Annual Report 2005

    International Nuclear Information System (INIS)

    Gudowski, Waclaw; Wallenius, Jan; Arzhanov, Vasily; Jolkkonen, Mikael; Eriksson, Marcus; Seltborg, Per; Westlen, Daniel; Lagerstedt, Christina; Isaksson, Patrick; Persson, Carl-Magnus; Aalander, Alexandra

    2006-11-01

    The results of the research activities on System and Safety of Accelerator-Driven Transmutation (ADS) at the Department of Nuclear and Reactor Physics are described in this report followed by the Appendices of the relevant scientific papers published in 2005. PhD and Licentiate dissertations of Marcus Ericsson, Per Seltborg, Christina Lagerstedt and Daniel Westlen (see Appendices) reflect the research mainstream of 2005. Year 2005 was also very rich in international activities with ADS in focus. Summary of conferences, seminars and lecturing activities is given in Chapter 9 Research activities of 2005 have been focused on several areas: system and safety studies of ADS; subcritical experiments; ADS source efficiency studies; nuclear fuel cycle analysis; potential of reactor based transmutation; ADS fuel development; simulation of radiation damage; and development of codes and methods. Large part of the research activities has been well integrated with the European projects of the 5th and 6th Framework Programmes of the European Commission in which KTH is actively participating. In particular European projects: RED-IMPACT, CONFIRM, FUTURE, EUROTRANS and NURESIM

  9. Undergraduate baccalaureate nursing students' self-reported confidence in learning about patient safety in the classroom and clinical settings: an annual cross-sectional study (2010-2013).

    Science.gov (United States)

    Lukewich, Julia; Edge, Dana S; Tranmer, Joan; Raymond, June; Miron, Jennifer; Ginsburg, Liane; VanDenKerkhof, Elizabeth

    2015-05-01

    Given the increasing incidence of adverse events and medication errors in healthcare settings, a greater emphasis is being placed on the integration of patient safety competencies into health professional education. Nurses play an important role in preventing and minimizing harm in the healthcare setting. Although patient safety concepts are generally incorporated within many undergraduate nursing programs, the level of students' confidence in learning about patient safety remains unclear. Self-reported patient safety competence has been operationalized as confidence in learning about various dimensions of patient safety. The present study explores nursing students' self-reported confidence in learning about patient safety during their undergraduate baccalaureate nursing program. Cross-sectional study with a nested cohort component conducted annually from 2010 to 2013. Participants were recruited from one Canadian university with a four-year baccalaureate of nursing science program. All students enrolled in the program were eligible to participate. The Health Professional Education in Patient Safety Survey was administered annually. The Health Professional Education in Patient Safety Survey captures how the six dimensions of the Canadian Patient Safety Institute Safety Competencies Framework and broader patient safety issues are addressed in health professional education, as well as respondents' self-reported comfort in speaking up about patient safety issues. In general, nursing students were relatively confident in what they were learning about the clinical dimensions of patient safety, but they were less confident about the sociocultural aspects of patient safety. Confidence in what they were learning in the clinical setting about working in teams, managing adverse events and responding to adverse events declined in upper years. The majority of students did not feel comfortable speaking up about patient safety issues. The nested cohort analysis confirmed these

  10. System and safety studies of accelerator driven transmutation. Annual Report 2003

    Energy Technology Data Exchange (ETDEWEB)

    Gudowski, Waclaw; Wallenius, Jan; Tucek, Kamil [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Nuclear and Reactor Physics] [and others

    2004-12-01

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the Dept. of Nuclear and Reactor Physics reported here has been focused on different aspects of safety of the Accelerator-Driven Transmutation Systems and on Transmutation research in more general terms. An overview of the topics of our research is given in the Summary which is followed by detailed reports as separate chapters or subchapters. Some of the research topics reported in this report are referred to appendices, which have been published in the open literature. Topics, which are not yet published, are described with more details in the main part of this report. Main focus has been, as before, largely determined by the programme of the European projects of the 5th Framework Programme in which KTH is actively participating. In particular: a) ADS core design and development of advanced nuclear fuel optimised for high transmutation rates and good safety features. This activity includes even computer modeling of nuclear fuel production. Three different ADS-core concept are being investigated: Conceptual design of Pb-Bi cooled core with nitride fuel so called Sing-Sing Core developed at KTH; Pb-Bi cooled core with oxide fuel so called ANSALDO design for the European Project PDS-XADS; Gas cooled core with oxide fuel a design investigated for the European Project PDS-XADS. b) analysis of potential of advance fuels, in particular nitrides with high content of minor actinides; c) analysis of ADS-dynamics and assessment of major reactivity feedbacks; d) emergency heat removal from ADS; e) participation in ADS: MUSE (CEA-Cadarache), YALINA subcritical experiment in Minsk and designing of the subcritical experiment SAD in Dubna; f) theoretical and simulation studies of radiation damage in high neutron (and/or proton) fluxes; g) computer code and nuclear data development relevant for simulation and optimization of ADS, validation of the MCB code and sensitivity analysis; h) studies of

  11. System and safety studies of accelerator driven transmutation. Annual Report 2003

    International Nuclear Information System (INIS)

    Gudowski, Waclaw; Wallenius, Jan; Tucek, Kamil

    2004-12-01

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the Dept. of Nuclear and Reactor Physics reported here has been focused on different aspects of safety of the Accelerator-Driven Transmutation Systems and on Transmutation research in more general terms. An overview of the topics of our research is given in the Summary which is followed by detailed reports as separate chapters or subchapters. Some of the research topics reported in this report are referred to appendices, which have been published in the open literature. Topics, which are not yet published, are described with more details in the main part of this report. Main focus has been, as before, largely determined by the programme of the European projects of the 5th Framework Programme in which KTH is actively participating. In particular: a) ADS core design and development of advanced nuclear fuel optimised for high transmutation rates and good safety features. This activity includes even computer modeling of nuclear fuel production. Three different ADS-core concept are being investigated: Conceptual design of Pb-Bi cooled core with nitride fuel so called Sing-Sing Core developed at KTH; Pb-Bi cooled core with oxide fuel so called ANSALDO design for the European Project PDS-XADS; Gas cooled core with oxide fuel a design investigated for the European Project PDS-XADS. b) analysis of potential of advance fuels, in particular nitrides with high content of minor actinides; c) analysis of ADS-dynamics and assessment of major reactivity feedbacks; d) emergency heat removal from ADS; e) participation in ADS: MUSE (CEA-Cadarache), YALINA subcritical experiment in Minsk and designing of the subcritical experiment SAD in Dubna; f) theoretical and simulation studies of radiation damage in high neutron (and/or proton) fluxes; g) computer code and nuclear data development relevant for simulation and optimization of ADS, validation of the MCB code and sensitivity analysis; h) studies of

  12. Monitoring of long range transported pollutants. Annual report for 1997; Overvaaking av langtransportert forurenset luft og nedboer. Atmosfaerisk tilfoersel, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Luekewille, A.; Manoe, S.; Toerseth, K

    1998-05-01

    The report includes the 1997 monitoring results from the rural air and precipitation chemistry network in Norway. In 1997, main components in precipitation were measured at 33 sites. Trace elements were determined at 14 sites, air concentrations of sulphur and nitrogen compounds at 13 sites and ozone concentrations at 14 sites. An overview of the measurement programme is given in appendix B2. The highest mean volume weighted concentrations of sulphate, nitrate, ammonium and strong acid in precipitation were found along the southern Norwegian coast. The lowest values were measured in the central and northern parts of Norway. In almost all parts of the country the mean pollutant concentrations in precipitation were generally lower in 1997 compared to 1996. At most places in Norway pollutant deposition was generally the lowest measured so far. The annual mean concentrations of sulphate and strong acid in precipitation have been decreasing since the end of the 1970's. Since 1980 the content of sulphate has decreased by about 40-55% in southern Norway and by about 50-60% in northern Norway. The observed reductions in concentration levels are in agreement with reported downwards trends in pollutant emissions in Europe. There is no significant decrease in nitrogen compounds in precipitation. Sea salts deposited along the western coast was measured. The highest content of particulate sulphate and of nitrogen components in air and precipitation were measured in southern Norway. Due to emissions from nickel smelters in Russia the mean concentrations of sulphur dioxide were highest in Finnmark. The annual mean air concentrations of particulate sulphate have generally decreased by 45 to 60% compared to those measured in 1980. At Ny-Aalesund, annual mean concentrations of sulphur dioxide and sulphate have decreased by 58% and 54%, respectively. Since the late 1970's, the mean concentrations have shown similar developments in all parts of Norway. Due to emission

  13. Monitoring of long range transported pollutants. Annual report for 1997; Overvaaking av langtransportert forurenset luft og nedboer. Atmosfaerisk tilfoersel, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Luekewille, A; Manoe, S; Toerseth, K

    1998-05-01

    The report includes the 1997 monitoring results from the rural air and precipitation chemistry network in Norway. In 1997, main components in precipitation were measured at 33 sites. Trace elements were determined at 14 sites, air concentrations of sulphur and nitrogen compounds at 13 sites and ozone concentrations at 14 sites. An overview of the measurement programme is given in appendix B2. The highest mean volume weighted concentrations of sulphate, nitrate, ammonium and strong acid in precipitation were found along the southern Norwegian coast. The lowest values were measured in the central and northern parts of Norway. In almost all parts of the country the mean pollutant concentrations in precipitation were generally lower in 1997 compared to 1996. At most places in Norway pollutant deposition was generally the lowest measured so far. The annual mean concentrations of sulphate and strong acid in precipitation have been decreasing since the end of the 1970's. Since 1980 the content of sulphate has decreased by about 40-55% in southern Norway and by about 50-60% in northern Norway. The observed reductions in concentration levels are in agreement with reported downwards trends in pollutant emissions in Europe. There is no significant decrease in nitrogen compounds in precipitation. Sea salts deposited along the western coast was measured. The highest content of particulate sulphate and of nitrogen components in air and precipitation were measured in southern Norway. Due to emissions from nickel smelters in Russia the mean concentrations of sulphur dioxide were highest in Finnmark. The annual mean air concentrations of particulate sulphate have generally decreased by 45 to 60% compared to those measured in 1980. At Ny-Aalesund, annual mean concentrations of sulphur dioxide and sulphate have decreased by 58% and 54%, respectively. Since the late 1970's, the mean concentrations have shown similar developments in all parts of Norway. Due to emission reductions in

  14. System and safety studies of accelerator driven transmutation systems. Annual report 1999

    International Nuclear Information System (INIS)

    Gudowski, Waclaw; Wallenius, Jan; Eriksson, Marcus; Carlsson, Johan; Seltborg, Per; Tucek, Kamil

    2000-05-01

    In 1996, SKB commenced funding of the project 'System and safety studies of accelerator driven transmutation systems and development of a spallation target'. The aim of the project was stated as: Development of a complete code for simulation of transmutation processes in an accelerator driven system. Application of the code for analysis of neutron flux, transmutation rates, reactivity changes, toxicity and radiation damages in the transmutation core. Build up of competence regarding issues related to spallation targets, development of research activities regarding relevant material issues. Performing of basic experiments in order to investigate the adequacy of using the spallation. target as a neutron source for a transmutation system, and participation in the planning and implementation of an international demonstration experiment. In the present report, activities within and related to the framework of the project, performed at the department of Nuclear and Reactor Physics at the Royal Institute of Technology during 1999, are accounted for

  15. Waste tank safety program annual status report for FY 1993, Task 5: Toxicology and epidemiology

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Young, J.Y.

    1993-09-01

    A toxicology team independently reviewed analytical data and provided advice concerning potential health effects associated with exposure to tank-vapor constituents at the Hanford site. Most of the emphasis was directed toward Tank 241-C-103, but a preliminary assessment was also made of the toxicologic implication of the cyanide levels in the headspace of Tank 241-C-108. The objectives of this program are to (1) review procedures used for sampling vapors from various tanks, (2) identify constituents in tank-vapor samples that could be related to symptoms reported by waste-tank workers, (3) evaluate the toxicologic implications of those constituents by comparison to established toxicologic data bases, (4) provide advice for additional analytical efforts, and (5) support other activities as requested by the project manager and the cognizant Westinghouse Hanford Company Tank Vapor Issues Safety Resolution Manager

  16. System and safety studies of accelerator driven transmutation systems. Annual report 1997

    International Nuclear Information System (INIS)

    Wallenius, J.; Carlsson, Johan; Gudowski, W.

    1997-12-01

    In November 1996, SKB started financing of the project ''System and safety studies of accelerator driven transmutation systems and development of a spallation target''. The aim of the project was stated as: 1) Development of a complete code for simulation of transmutation processes in an accelerator driven system. Application of the code for analysis of neutron flux, transmutation rates, reactivity changes, toxicity and radiation damages in the transmutation core. 2) Build up of competence regarding issues related to spallation targets development of research activities regarding relevant material issues. Performing of basic experiments in order to investigate the adequacy of using the spallation target as a neutron source for a transmutation system, and participation in the planning and implementation of an international demonstration-experiment. In the present report, activities within the framework of the project performed at the department of Nuclear and Reactor Physics at the Royal Institute of Technology during 1997, are accounted for

  17. System and safety studies of accelerator driven transmutation systems. Annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Wallenius, J.; Carlsson, Johan; Gudowski, W. [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    1997-12-01

    In November 1996, SKB started financing of the project ``System and safety studies of accelerator driven transmutation systems and development of a spallation target``. The aim of the project was stated as: 1) Development of a complete code for simulation of transmutation processes in an accelerator driven system. Application of the code for analysis of neutron flux, transmutation rates, reactivity changes, toxicity and radiation damages in the transmutation core. 2) Build up of competence regarding issues related to spallation targets development of research activities regarding relevant material issues. Performing of basic experiments in order to investigate the adequacy of using the spallation target as a neutron source for a transmutation system, and participation in the planning and implementation of an international demonstration-experiment. In the present report, activities within the framework of the project performed at the department of Nuclear and Reactor Physics at the Royal Institute of Technology during 1997, are accounted for. 13 refs, 6 figs.

  18. System and safety studies of accelerator driven transmutation systems. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Gudowski, Waclaw; Wallenius, Jan; Eriksson, Marcus; Carlsson, Johan; Seltborg, Per; Tucek, Kamil [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    2000-05-01

    In 1996, SKB commenced funding of the project 'System and safety studies of accelerator driven transmutation systems and development of a spallation target'. The aim of the project was stated as: Development of a complete code for simulation of transmutation processes in an accelerator driven system. Application of the code for analysis of neutron flux, transmutation rates, reactivity changes, toxicity and radiation damages in the transmutation core. Build up of competence regarding issues related to spallation targets, development of research activities regarding relevant material issues. Performing of basic experiments in order to investigate the adequacy of using the spallation. target as a neutron source for a transmutation system, and participation in the planning and implementation of an international demonstration experiment. In the present report, activities within and related to the framework of the project, performed at the department of Nuclear and Reactor Physics at the Royal Institute of Technology during 1999, are accounted for.

  19. Environment, safety, health at DOE Facilities. Annual report, Fiscal Year 1980

    International Nuclear Information System (INIS)

    1981-07-01

    The Department of Energy's occupational safety and property protection performance in fiscal year 1980 was excellent in all reported categories with loss rates generally less than one-third of comparable industry figures. The Department of Energy's fiscal year 1980 incidence rate per 200,000 work hours was 1.1 lost workday cases and 18.2 lost workdays compared to 1.1 lost workday cases and 17.2 lost workdays during fiscal year 1979. The recorded occupational illness rate, based on only 70 cases, was 0.05 cases per 200,000 work hours compared to 0.06 cases per 200,000 work hours for fiscal year 1979. Ten fatalities involving Federal or contractor employees occurred in fiscal year 1980 compared to nine for fiscal year 1979. Four of those in fiscal year 1980 resulted from two aircraft accidents. Total reported property loss during fiscal year 1980 was $7.1 million with $3.5 million attributable to earthquake damage sustained by the Lawrence Livermore and Sandia National Laboratories on January 24, 1980. A total of 131 million vehicle miles of official vehicular travel during fiscal year 1980 resulted in 768 accidents and $535,145 in property damages. The 104,986 monitored Department of Energy and Department of Energy contractor employees received a total dose of 9040 REM in calendar year 1979. Both the total dose and the 1748 employees receiving radiation exposures greater than 1 REM in 1979 represent a continuing downward trend from the calendar year 1978 total dose of 9380 REM and the 1826 employees who received radiation exposures greater than 1 REM. The fifty-nine appraisals conducted indicate that generally adequate plans have been developed and effective organizational structures have been established to carry out the Department of Energy's Environmental Protection, Safety, and Health Protection (ES and H) Program

  20. 47{sup th} Annual conference on nuclear technology (AMNT 2016). Key topics / Outstanding know-how and sustainable innovations - enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Raetzke, Christian [CONLAR - Consulting on Nuclear Law, Licensing and Regulation, Leipzig (Germany); Fischer, Erwin [PreussenElektra GmbH, Hannover (Germany). Management Board; Mohrbach, Ludger [VGB PowerTech e.V., Essen (Germany). Competence Center ' ' Nuclear Power Plants' '

    2016-08-15

    Summary report on the Key Topics ''Outstanding Know-How and Sustainable Innovations'' and ''Enhanced Safety and Operation Excellence'' of the 47{sup th} Annual Conference on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 will be covered in further issues of atw.

  1. Mining and mining authorities in Saarland 2016. Mining economy, mining technology, occupational safety, environmental protection, statistics, mining authority activities. Annual report

    International Nuclear Information System (INIS)

    2016-01-01

    The annual report of the Saarland Upper Mining Authority provides an insight into the activities of mining authorities. Especially, the development of the black coal mining, safety and technology of mining as well as the correlation between mining and environment are stressed.

  2. 48{sup th} Annual meeting on nuclear technology (AMNT 2017). Key topic / Enhanced safety and operation excellence. Focus session: International operational experience

    Energy Technology Data Exchange (ETDEWEB)

    Mohrbach, Ludger [VGB PowerTech e.V., Essen (Germany). Abteilung ' ' N' ' ; Gottschling, Helge

    2017-11-15

    Summary report on the Key Topic Enhanced Safety and Operation Excellence: Focus Session: International Operational Experience and the Nuclear Energy Campus of the 48{sup th} Annual Meeting on Nuclear Technology (AMNT 2017) held in Berlin, 16 to 17 May 2017.

  3. Status of safety at Areva group facilities. 2006 annual report; Etat de surete des installations nucleaires. Rapport annuel 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This report presents a snapshot of nuclear safety and radiation protection conditions in the AREVA group's nuclear installations in France and abroad, as well as of radiation protection aspects in service activities, as identified over the course of the annual inspections and analyses program carried out by the General Inspectorate in 2006. This report is presented to the AREVA Supervisory Board, communicated to the labor representation bodies concerned, and made public. In light of the inspections, appraisals and coordination missions it has performed, the General Inspectorate considers that the nuclear safety level of the AREVA group's nuclear installations is satisfactory. It particularly noted positive changes on numerous sites and efforts in the field of continuous improvement that have helped to strengthen nuclear safety. This has been possible through the full involvement of management teams, an improvement effort initiated by upper management, actions to increase personnel awareness of nuclear safety culture, and supervisors' heightened presence around operators. However, the occurrence of certain events in facilities has led us to question the nuclear safety repercussions that the changes to activities or organization on some sites have had. In these times of change, drifts in nuclear safety culture have been identified. The General Inspectorate considers that a preliminary analysis of the human and organizational factors of these changes, sized to match the impact the change has on nuclear safety, should be made to ensure that a guaranteed level of nuclear safety is maintained (allowance for changes to references, availability of the necessary skills, resources of the operating and support structures, etc.). Preparations should also be made to monitor the changes and spot any telltale signs of drift in the application phase. Managers should be extra vigilant and the occurrence of any drift should be systematically dealt with ahead of

  4. Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

  5. Impact of Continuous Cropping on the Diurnal Range of Dew Point Temperature during the Foliar Expansion Period of Annual Crops on the Canadian Prairies

    Directory of Open Access Journals (Sweden)

    Bharat M. Shrestha

    2016-01-01

    Full Text Available It is important to increase our knowledge of the role of land use in changing the regional climate. This study asked, “Has the increase in continuous cropping over the past 50 years on the Canadian Prairies influenced the daily mean and range of morning dew point temperatures (Td during the foliar expansion period (from mid-June to mid-July of annual field crops?” We found that there has been a general increase in the decadal average of mean daily Td and in the range of morning Td from the 1960s to the 2000s. The increase in the observed range of Td between the daily minimum value, which typically occurs near sunrise, and the late morning peak was found to be related to the increase in annual crop acreage and consequent decrease in summerfallow area. The relationship was more significant in the subhumid climatic zone than in the semiarid climatic zone, and it was influenced by whether the region was experiencing either wet, normal, or dry conditions.

  6. Environment, safety, and health at DOE facilities. Annual report, calendar year 1981

    International Nuclear Information System (INIS)

    1982-10-01

    During 1981 the US Department of Energy's (DOE) safety and property protection performance remained excellent in all reported categories with loss rates generally less than one-third of comparable private-industry rates. The 1981 occupational-injury rates of 1.0 lost-workday cases and 13.5 lost workdays per 200,000 work hours were better than 1980 rates of 1.1 lost-workday cases and 17.5 lost workdays per 200,000 work hours. The recorded occupational illness rate, based on only 61 cases in 1981, was 0.04 cases per 200,000 work hours compared to 0.06 cases per 200,000 work hours for 1980. Property losses during 1981 totaled $4.7 million, with the largest loss of $1.25 million resulting from a fire at a Bonneville Power Administration lighting substation in Ellenberg, Washington. Fire losses during 1981 totaled $2.01 million, resulting in a fire loss rate of 0.38 cent per $100 property valuation - about one-eight the best class private-sector rate. Non-fire losses during 1981 totaled $2.65 million. The resulting non-fire loss rate of 0.48 cent per $100 property valuation was approx. one-third (36%) the 1980 loss rate of 1.34 cents per $100 property valuation. The 82,873 monitored Department of Energy federal and contractor employees received a total radiation dose of 6902 rem in 1981. The total amount of effluent radioactivity released from all DOE facilities in 1981 was 1.9 million curies, compared to 1.4 million curies in 1980. The largest probable whole-body radiation dose received by a maximally exposed public individual from any of these facilities was the same as in 1980: 15 millirem, or 3% of the DOE Radiation Protection Guide standard. A major accomplishemet during 1981 was the successful pilot testing of the Computerized Accident/Incident Reporting System (CAIRS), which will provide more-comprehensive safety information than the present data system

  7. Organic tank safety project: Equilibrium moisture determination task. FY 1998 annual progress report

    International Nuclear Information System (INIS)

    Scheele, R.D.; Bredt, P.R.; Sell, R.L.

    1998-08-01

    During fiscal year 1998, PNNL investigated the effect of P H 2 O at or near maximum tank waste surface temperatures on the equilibrium water content of selected Hanford waste samples. These studies were performed to determine how dry organic-bearing wastes will become if exposed to environmental Hanford water partial pressures. The samples tested were obtained from Organic Watch List Tanks. At 26 C, the lowest temperature used, the water partial pressures ranged from 2 to 22 torr. At 41 C, the highest temperature used, the water partial pressures ranged from 3.5 to 48 torr. When the aliquots exposed to the lowest and highest water partial pressures reached their equilibrium or near-equilibrium water contents, they were exchanged to determine if hysteresis occurred. In some experiments, once equilibrated, aliquots not used in the hysteresis experiments were allowed to equilibrate at room temperature (23 C) until the hysteresis experiments ended; this provides a measure of the effect of temperature

  8. System and safety studies of accelerator driven systems for transmutation. Annual report 2008

    International Nuclear Information System (INIS)

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

    2009-07-01

    Within this project, research on design and safety of subcritical reactors for recycling of minor actinides is performed. During 2008, the reactor physics division at KTH has made a design study of a source efficient ADS with nitride fuel, based on the EFIT design made within the EUROTRANS project. Transient analysis for EFIT-400 ADS with cercer and cermet fuels was made with SAS4A, taking into account flow reversal phenomena. Using Pulsed Neutron Source techniques, reference reactivity values for detectors in the sub-critical YALINA booster facility were obtained and it was observed that the results carry strong spatial effects. It was shown that the beam trip technique can be used to obtain the reactivity at beam trips and the values can be used for calibration of a current-to-flux reactivity indicator. Multi-scale modelling of helium desorption from molybdenum was performed, with the final aim to predict the in-pile behaviour of Mo based CERMET fuel. Good agreement with experimental data was obtained, except at the highest temperatures

  9. System and safety studies of accelerator driven systems for transmutation. Annual report 2008

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-15

    Within this project, research on design and safety of subcritical reactors for recycling of minor actinides is performed. During 2008, the reactor physics division at KTH has made a design study of a source efficient ADS with nitride fuel, based on the EFIT design made within the EUROTRANS project. Transient analysis for EFIT-400 ADS with cercer and cermet fuels was made with SAS4A, taking into account flow reversal phenomena. Using Pulsed Neutron Source techniques, reference reactivity values for detectors in the sub-critical YALINA booster facility were obtained and it was observed that the results carry strong spatial effects. It was shown that the beam trip technique can be used to obtain the reactivity at beam trips and the values can be used for calibration of a current-to-flux reactivity indicator. Multi-scale modelling of helium desorption from molybdenum was performed, with the final aim to predict the in-pile behaviour of Mo based CERMET fuel. Good agreement with experimental data was obtained, except at the highest temperatures

  10. Ferrocyanide safety project task 3 ferrocyanide aging studies FY 1994 annual report

    International Nuclear Information System (INIS)

    Lilga, M.A.; Alderson, E.V.; Kowalski, D.J.; Lumetta, M.R.; Schiefelbein, G.F.

    1994-09-01

    The research performed for this project is part of an effort begun in the mid-1980s to characterize the materials stored in the single-shell waste storage tanks (SSTs) at the U.S. Department of Energy (DOE) Hanford Site. Various radioactive wastes from defense operations have accumulated at the Hanford Site in underground waste tanks since the early 1940s. The goal of the Aging Studies task is to understand the long-term chemical and radiolytic behavior of ferrocyanide tank wastes in the SST environments. In turn, this information provides baseline data that will be useful as actual SST samples are obtained and analyzed. The results of aging studies will directly assist in determining which strategy will assure safe storage of the ferrocyanide waste in the tanks and how the ferrocyanide safety issue can be resolved. This report contains the results of FY 1994 research for the Aging Studies task, which focused on the hydrolysis of ferrocyanide waste simulants in aqueous base. Hydrolysis was investigated in 2M NaOH as a function of temperature, applied gamma dose rate, and soluble Fe(CN) 6 -4 concentration. A hydrolysis experiment was conducted at pH 10 and another in the presence of aluminum. In addition, experiments investigating cesium ion exchange in competition with sodium nickel ferrocyanide dissolution were conducted

  11. Study on post-earthquake plant evaluation and communication (Annual safety research report, JFY 2011)

    International Nuclear Information System (INIS)

    2012-01-01

    The aims of this study are to establish a post-earthquake plant evaluation method and to develop a communication system for the improving seismic safety regulations as well as encouraging public communication. The Miyagiken-oki earthquake in 2005, Onagawa Nuclear Power Plant shut down automatically. Subsequently, JNES started development of post-earthquake plant evaluation and communication system based on the experience of the cross-check analysis for Onagawa Nuclear Power Plant. The Niigata-ken Chuetsu-oki Earthquake in 2007, the plant situation was not transmitted promptly. The loss of information sharing between local community and related organizations caused the public anxiety. The importance of plant information transmission as well as seismic information gathering were recognized. The proposal for the solution of the information issues were performed by government committee, In this study the evaluation method for soundness of the main structure and equipment after earthquake event were updated. Moreover, information dissemination to the public and transparent communication methodology was examined by the Industry-Academia-Government cooperation in the Kashiwazaki-Kariwa region. (author)

  12. Study on post-earthquake plant evaluation and communication (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    Iijima, Toru; Taoka, Hideto; Yamada, Hiroyuki; Sano, Kyoko

    2011-01-01

    The aims of this study are to establish a post-earthquake plant evaluation method and to develop a communication system for the improving seismic safety regulations as well as encouraging public communication. The Miyagiken-oki earthquake in 2005, Onagawa Nuclear Power Plant shut down automatically. Subsequently, JNES started development of post-earthquake plant evaluation and communication system based on the experience of the cross-check analysis for Onagawa Nuclear Power Plant. The Niigata-ken Chuetsu-oki Earthquake in 2007, the plant situation was not transmitted promptly. The loss of information sharing between local community and related organizations caused the public anxiety. The importance of plant information transmission as well as seismic information gathering were recognized. The proposal for the solution of the information issues were performed by government committee. In this study, the evaluation method for soundness of the main structure and equipment after earthquake event were updated. Moreover, procedure of the post-earthquake plant soundness evaluation and multi-functional seismic information system were developed. In addition, the implementation strategy of the easy-to -understand information dissemination to the public and transparent communication methodology was examined by the Industry-Academia-Government cooperation in the Kashiwazaki-Kariwa region. (author)

  13. Annual report on reactor safety research projects sponsored by the Minister for Research and Technology of the Federal Republic of Germany 1989

    International Nuclear Information System (INIS)

    1990-08-01

    Investigations on the safety of light water reactors (LWR) being performed in the framework of his research program on reactor safety are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT) (Federal Minister for Research and Technology). Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks also projects on the safety of advanced reactors are sponsored by the BMFT. The Gesellschaft fuer Reaktorsicherheit (GRS), (Society for Reactor Safety), by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP)

  14. System and safety studies of accelerator driven transmutation. Annual Report 2002

    International Nuclear Information System (INIS)

    Gudowski, W.; Wallenius, J.; Tucek, K.; Eriksson, Marcus; Carlsson, Johan; Seltborg, P.; Cetnar, J.; Chakarova, R.; Jollkonen, Mikael; Westlen, D.

    2003-06-01

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the Dept. of Nuclear and Reactor Physics has been largely determined by the program of the European projects of the the 5th Framework Programme. In particular: a) ADS core design and development of advanced nuclear fuel optimized for high transmutation rates and good safety features. This activity includes computer modeling of nuclear fuel production. Three different ADS-core concept are being investigated: Conceptual design of Pb-Bi cooled core with nitride fuel - so called Sing-Sing Core; Pb-Bi cooled core with oxide fuel; Gas cooled core with oxide fuel - both designs investigated for the European Project PDS-XADS; b) analysis of ADS-dynamics and assessment of major reactivity feedbacks; c) emergency heat removal from ADS; d) participation in ADS experiments including 1 MW spallation target manufacturing, subcritical experiments MUSE, YALINA subcritical experiment in Minsk and designing of the subcritical experiment SAD in Dubna; e) material studies for ADS, in particular theoretical and simulation studies of radiation damage in high neutron (or proton) fluxes; f) computer code and nuclear data development relevant for simulation and optimization of ADS, special efforts were put in the frame of the European Project PDS-XADS to perform sensitivity studies of the different nuclear data libraries; g) studies of transmutation potential of critical reactors in particular High Temp Gas Cooled Reactor. Most important finding and conclusions from our studies: A strong positive void coefficient was found for lead/bismuth cooled cores. This considerable void effect is attributed to a high fraction of americium (60%) in the fuel. It was found that void reactivity insertion rates increases with P/D; in response to the beam overpower accident the Pb/Bi-cooled core featured the twice longer grace time compared to the sodium-cooled core; an important safety issue is the high void worth that could

  15. System and safety studies of accelerator driven transmutation. Annual Report 2002

    Energy Technology Data Exchange (ETDEWEB)

    Gudowski, W.; Wallenius, J.; Tucek, K.; Eriksson, Marcus; Carlsson, Johan; Seltborg, P.; Cetnar, J.; Chakarova, R.; Jollkonen, Mikael; Westlen, D. [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    2003-06-01

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the Dept. of Nuclear and Reactor Physics has been largely determined by the program of the European projects of the the 5th Framework Programme. In particular: a) ADS core design and development of advanced nuclear fuel optimized for high transmutation rates and good safety features. This activity includes computer modeling of nuclear fuel production. Three different ADS-core concept are being investigated: Conceptual design of Pb-Bi cooled core with nitride fuel - so called Sing-Sing Core; Pb-Bi cooled core with oxide fuel; Gas cooled core with oxide fuel - both designs investigated for the European Project PDS-XADS; b) analysis of ADS-dynamics and assessment of major reactivity feedbacks; c) emergency heat removal from ADS; d) participation in ADS experiments including 1 MW spallation target manufacturing, subcritical experiments MUSE, YALINA subcritical experiment in Minsk and designing of the subcritical experiment SAD in Dubna; e) material studies for ADS, in particular theoretical and simulation studies of radiation damage in high neutron (or proton) fluxes; f) computer code and nuclear data development relevant for simulation and optimization of ADS, special efforts were put in the frame of the European Project PDS-XADS to perform sensitivity studies of the different nuclear data libraries; g) studies of transmutation potential of critical reactors in particular High Temp Gas Cooled Reactor. Most important finding and conclusions from our studies: A strong positive void coefficient was found for lead/bismuth cooled cores. This considerable void effect is attributed to a high fraction of americium (60%) in the fuel. It was found that void reactivity insertion rates increases with P/D; in response to the beam overpower accident the Pb/Bi-cooled core featured the twice longer grace time compared to the sodium-cooled core; an important safety issue is the high void worth that could

  16. Annual report on Reactor Safety Research Projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 1999. Progress report

    International Nuclear Information System (INIS)

    2000-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technologie (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to the classification system ''Joint Safety Research Index'' of the CEC (commission of the European communities). The reports are arranged in sequence of their project numbers. (orig.)

  17. Safety

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

  18. Annual report for FY 2010 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2010 - March 31, 2011

    International Nuclear Information System (INIS)

    2012-03-01

    This annual report describes the activities of Radiation Protection Sector in Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The research and development activities obtained certain results in the fields of operational radiation protection technique and the construction of calibration fields for neutron beams. The institutes in Tokai, Takasaki, Aomori and Naka were suffered from the Great East Japan Earthquake and the nuclear power plant accident which followed the earthquake. (author)

  19. 46{sup th} annual meeting on nuclear technology (AMNT 2015). Key topics / Outstanding know-how and sustainable innovations enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Lamm, Matthias [AREVA GmbH, Erlangen (Germany). R and D; Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Reactor Safety Research Div.

    2016-01-15

    Summary report on the Technical Sessions ''Know-how, New Build and Innovations'' and ''Operation and Safety of Nuclear Installations, Fuel SA: WASA-BOSS + CESAM'' of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015. Other Sessions of AMNT 2015 have been covered in atw 7 to 12 (2015) and will be covered in further issues of atw.

  20. 46{sup th} Annual meeting on nuclear technology (AMNT 2015). Key topics / Outstanding know-how and sustainable innovations / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Schaffrath, Andreas; Scheuerer, Martina [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Garching (Germany); Oenneby Carina; Benjaminsson, Ulf [Westinghouse Electric Sweden AB, Vaesteraes (Sweden). Europe, Middle East and Africa (EMEA)

    2015-11-15

    Summary report on the Topical Sessions ''CFD Simulations for Reactor Safety Relevant Objectives '' and ''Fuel Management During the Last Cycles and Beyond'' of the 46th Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015. Other Sessions of AMNT 2015 have been covered in atw 7 to 10 (2015) and will be covered in further issues of atw.

  1. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence and decommissioning experience and Waste management solutions

    Energy Technology Data Exchange (ETDEWEB)

    Salnikova, Tatiana [AREVA GmbH, Erlangen (Germany); Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)

    2016-10-15

    Summary report on the Key Topics ''Enhanced Safety and Operation Excellence'' and ''Decommissioning Experience and Waste Management Solutions'' of the 47{sup th} Annual Conference on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

  2. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 2005. Progress report

    International Nuclear Information System (INIS)

    2005-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  3. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

    International Nuclear Information System (INIS)

    2004-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  4. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  5. Annual report on reactor safety research projects sponsored by the Ministry for Research and Technology of the Federal Republic of Germany 1987

    International Nuclear Information System (INIS)

    1988-06-01

    The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress-Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the Research Program on the Safety of LWRs of the BMFT. Another table of contents uses the same classification system as applied in the Nuclear Safety Index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The report are arranged in the sequence of their project numbers. (orig./HP) [de

  6. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2003. Progress report

    International Nuclear Information System (INIS)

    2003-01-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers

  7. Efficacy and Safety of OnabotulinumtoxinA Treatment of Forehead Lines: A Multicenter, Randomized, Dose-Ranging Controlled Trial.

    Science.gov (United States)

    Solish, Nowell; Rivers, Jason K; Humphrey, Shannon; Muhn, Channy; Somogyi, Chris; Lei, Xiaofang; Bhogal, Meetu; Caulkins, Carrie

    2016-03-01

    Various onabotulinumtoxinA doses are effective in treating forehead lines (FHL), with a trend toward lower doses. To evaluate efficacy and safety of onabotulinumtoxinA dose-ranging treatment of FHL when the frontalis area and glabellar complex are treated together. Adults with moderate-to-severe FHL received onabotulinumtoxinA 40 U (FHL, 20 U; glabellar lines [GL], 20 U), 30 U (FHL, 10 U; GL, 20 U), or placebo. Response was assessed at weeks 1, 2, day 30, and monthly to day 180. Coprimary efficacy end points were investigator- and subject-assessed Facial Wrinkle Scale scores of none or mild (day 30). Patient-reported outcomes, onset/duration of effect, and adverse events (AEs) were evaluated. Responder rates (investigator/subject, respectively) were 40-U group, 91.2%/89.5%; 30-U group, 86.4%/81.4%; placebo, 1.7%/5.1%. OnabotulinumtoxinA resulted in significantly greater responder rates than placebo (p < .001). Adverse events were mild to moderate and similar between groups (most common AEs: nasopharyngitis [4.6%] and headache [4.0%]). Treatment of FHL with onabotulinumtoxinA 40 and 30 U (in frontalis and glabellar complex muscles) was tolerable, effective, and sustained. Both doses significantly reduced FHL severity; however, the 40-U dose demonstrated a trend toward greater sustained benefit and longer duration of effect versus the 30-U dose, with similar AE rates.

  8. 7th annual report 1998. UN ECE convention on long-range transboundary air pollution. International cooperative programme on integrated monitoring of air pollution effects on ecosystems

    Energy Technology Data Exchange (ETDEWEB)

    Kleemola, S.; Forsius, M. [eds.

    1998-11-01

    The Integrated Monitoring Programme (ICP IM) is part of the Effects Monitoring Strategy under the UN ECE Long-Range Transboundary Air Pollution Convention. The main aim of ICP IM is to provide a framework to observe and understand the complex changes occurring in the external environment. The monitoring and prediction of complex ecosystem effects on undisturbed reference areas require a continuous effort to improve the collection and assessment of data on the international scale. At the 1997 Task Force meeting it was decided that future annual reports from ICP IM would have a more technical character. The report could include some scientific material but also short technical descriptions of recent national activities and publications. Scientific articles should preferably be published in recognised scientific journals. The responsibility for producing annual reports would still lie on the Programme Centre, but more contributions from National Focal Points were welcomed. The content of the present Annual Report reflects the decisions of the Task Force meeting. The report gives a general overview of the ICP IM activities, the present content of the ICP IM database, and presents results from assessment activities carried out by several collaborating institutes and the ICP IM Programme Centre during the programme year 1997/98. The resources of the Programme Centre have been targeted to the revision of the Programme Manual and the EU/LIFE-project `Development of Assessment and Monitoring Techniques at Integrated Monitoring Sites in Europe`, which has limited the possibilities to carry out additional evaluations of ICP IM data. Section 1 is a short status report of the ICP IM activities, content of the IM database, including the contents of the GIS database, and the present geographical coverage of the monitoring network. Section 2 contains a report on multivariate gradient analysis applied to relate chemical and biological observations (prepared by D. de Zwart, RIVM

  9. Probabilistic methods applied to the safety of nuclear power plant: annual report - 1980. Part. 1: theoretical fundaments

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Hesles, J.B.S.; Milidiu, R.L.; Maciel, C.C.; Gibelli, S.M.O.; Oliveira, L.C.; Fleming, P.V.; Rivera, R.R.J.

    1981-02-01

    The probabilistic Safety Analysis Group from COPPE was founded in 1980. This first part of the report shows the theoretical fundaments used for reliability analysis of some safety systems for Angra-1 [pt

  10. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 2007. Progress report

    International Nuclear Information System (INIS)

    2007-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Research Management Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system 'Joint Safety Research Index (JSRI)'. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  11. A semi annual report on the activities in safety administration division. Report of the second half of 2004

    International Nuclear Information System (INIS)

    Yamamoto, Junta

    2005-07-01

    The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in October, 2004 to March, 2005. (author)

  12. SAFETY

    CERN Multimedia

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

  13. 33 CFR 165.941 - Safety Zones; Annual Fireworks Events in the Captain of the Port Detroit Zone.

    Science.gov (United States)

    2010-07-01

    ... times for this event will be determined annually. (5) Alpena Fireworks, Alpena, MI: (i) Location: All... Alpena, MI. (ii) Expected date: One evening during the last week in of June or the first week of July...

  14. 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.

  15. 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.

  16. Annual report on reactor safety research projects sponsored by the Ministry for Research and Technology of the Federal Republic of Germany. Reporting period 1993. Progress report

    International Nuclear Information System (INIS)

    1994-10-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general information of progress in reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP)

  17. 46th Annual meeting on nuclear technology (AMNT 2015). Key topic / Enhanced safety and operation excellence / Sustainable reactor operation management - safe, efficient, valuable

    International Nuclear Information System (INIS)

    Fischer, Erwin

    2015-01-01

    Summary report on the following Topical Session of the 46 th Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015: - Sustainable Reactor Operation Management - Safe, Efficient, Valuable (Erwin Fischer) The other Sessions of the Key Topics - ''Outstanding Know-How and Sustainable Innovations'', - ''Enhanced Safety and Operation Excellence'' and - ''Decommissioning Experience and Waste Management Solutions'' have been covered in atw 7 (2015) and will be covered in further issues of atw.

  18. 46{sup th} Annual meeting on nuclear technology (AMNT 2015). Key topic / Enhanced safety and operation excellence / Sustainable reactor operation management - safe, efficient, valuable

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, Erwin [E.ON Kernkraft GmbH, Global Unit Next Generation, Hannover (Germany)

    2015-08-15

    Summary report on the following Topical Session of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015: - Sustainable Reactor Operation Management - Safe, Efficient, Valuable (Erwin Fischer) The other Sessions of the Key Topics - ''Outstanding Know-How and Sustainable Innovations'', - ''Enhanced Safety and Operation Excellence'' and - ''Decommissioning Experience and Waste Management Solutions'' have been covered in atw 7 (2015) and will be covered in further issues of atw.

  19. 48{sup th} Annual meeting on nuclear technology (AMNT 2017). Key topic / Enhanced safety and operation excellence. Technical session: Operation and safety of nuclear installations, fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Bereich Reaktorsicherheitsforschung

    2017-12-15

    The sessions Fuel and Materials and Containment and SFP, as part of the Technical Sessions Operation and Safety of Nuclear Installations, Fuel implemented in the Key Topic Enhanced Safety and Operation Excellence were chaired by Dr. Thorsten Hollands (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH) and Dr. Erwin Fischer (PreussenElektra GmbH) who was the keynote coordinator for the Technical Sessions. Both sessions consist of a keynote lecture followed by technical presentations.

  20. Annual report for FY 2012 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2012 - March 31, 2013

    International Nuclear Information System (INIS)

    2014-02-01

    This annual report describes the activities in the 2012 fiscal year of Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection practices in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The radiological situations at the institutes in Tokai, Aomori and Naka have been affected by the Fukushima Dai-ichi nuclear power plant accident in March 2011. The research and development activities produced certain results in the fields of radiation protection technique. The radiation protection experts in the institutes actively participated in the projects after the Fukushima nuclear power plant accident. (author)

  1. Annual report for FY 2012 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2012 - March 31, 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-02-15

    This annual report describes the activities in the 2012 fiscal year of Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection practices in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The radiological situations at the institutes in Tokai, Aomori and Naka have been affected by the Fukushima Dai-ichi nuclear power plant accident in March 2011. The research and development activities produced certain results in the fields of radiation protection technique. The radiation protection experts in the institutes actively participated in the projects after the Fukushima nuclear power plant accident. (author)

  2. 46{sup th} Annual meeting on nuclear technology (AMNT 2015). Key Topic / Enhanced safety and operation excellence / Radiation protection

    Energy Technology Data Exchange (ETDEWEB)

    Baumann, Erik [AREVA GmbH, Erlangen (Germany). Radiation Protection; Bohnsted, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Safety Research for Nuclear Waste Management, Radiation Protection

    2015-10-15

    Summary report on the Focus Session 'Radiation Protection' of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015. Other Sessions of AMNT 2015 have been covered in atw 7 and 8 (2015) and will be covered in further issues of atw.

  3. 33 CFR 165.939 - Safety Zones; Annual Fireworks Events in the Captain of the Port Buffalo Zone.

    Science.gov (United States)

    2010-07-01

    ..., 081°21.400′ W (west of the harbor entrance); in Mentor Harbor, OH. (DATUM: NAD 83). (ii) Enforcement... Captain of the Port or his designated representative to enter, move within, or exit the safety zone...

  4. Annual report on reactor safety research projects sponsored by the Ministry for Research and Technology of the Federal Republic of Germany 1988

    International Nuclear Information System (INIS)

    1989-06-01

    The GRS (Society for Reactor Safety), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department) Forschungsbetreuung at the GRS, within the framework of general information of progress in the reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. Besides the progress reports, lists of reports exchanged under international exchange agreements by the BMFT are published within this series. (orig./HP)

  5. Pacific Northwest Laboratory annual report for 1988 to the Assistant Secretary for Environment, Safety, and Health: Part 5, Environment, safety, health, and quality assurance

    Energy Technology Data Exchange (ETDEWEB)

    Faust, L.G.; Pennell, W.T.; Selby, J.M.

    1989-02-01

    This document summarizes the research programs now underway at Battelle's Pacific Northwest Laboratory in the areas of environmental safety, health, and quality assurance. Topics include internal irradiation, emergency plans, dose equivalents, risk assessment, dose equivalents, surveys, neutron dosimetry, and radiation accidents. (TEM)

  6. Pacific Northwest Laboratory annual report for 1988 to the Assistant Secretary for Environment, Safety, and Health: Part 5, Environment, safety, health, and quality assurance

    International Nuclear Information System (INIS)

    Faust, L.G.; Pennell, W.T.; Selby, J.M.

    1989-02-01

    This document summarizes the research programs now underway at Battelle's Pacific Northwest Laboratory in the areas of environmental safety, health, and quality assurance. Topics include internal irradiation, emergency plans, dose equivalents, risk assessment, dose equivalents, surveys, neutron dosimetry, and radiation accidents

  7. Safety of the French power grid: audit and annual reporting; Surete du systeme electrique francais: audit et reporting annuel

    Energy Technology Data Exchange (ETDEWEB)

    Tesseron, J.M. [Reseau de Transport d' Electricite (RTE), 92 - Paris la Defense (France)

    2006-09-15

    Power system reliability is at the core of the responsibilities entrusted to RTE, the French transmission system operator. Considering the particularly important issue of reliability, RTE's management has set up an entity which reports to it directly on this subject. The two main activities of this entity involve drawing up the annual system reliability report and carrying out audits devoted to reliability. After going over the principles governing the control of system reliability in France, the document presents the experience acquired since 2000. The principles underlying the drafting of the annual reliability report and the method for scheduling and performing the reliability audits are first set out. The author then goes on to present how these principles are applied to two reliability audits, one carried out on voltage control and the other on the control of the clearance time of short-circuits affecting the 400 kV grid. (author)

  8. Compilation of contract research for the Materials Branch, Division of Engineering Safety: Annual report for FY 1986

    International Nuclear Information System (INIS)

    1987-03-01

    This report presents summaries of the research work performed during Fiscal Year 1986 by laboratories and organizations under contracts administered by the NRC's Materials Branch, Office of Nuclear Regulatory Research. Each contractor has written a more complete and detailed annual report of their work which can be obtained by writing to NRC; however, we believe it is useful to have a summary of each contractor's efforts for the year combined into one volume

  9. The Aube Storage Centre. Information report on nuclear safety and radiation protection for 2014 - Annual report 2014

    International Nuclear Information System (INIS)

    2014-06-01

    After a presentation of the installations of CSA (Aube Storage Centre), its equipment, its exploitation (deliveries, storage, compacting unit, injection unit, storage works), works performed and highlights in 2014, and perspectives of evolution for 2015 and 2016, this report presents the measures regarding nuclear safety: safety principles, technical measures to meet objectives, inspections performed by the Nuclear Safety Authority (ASN), and quality management. The next part presents measures regarding measures for radiation protection and safety: staff dosimetry (measurements results and evolutions), safety exercise. It outlines that no important incident occurred, and described three minor events which have been declared to the ASN. The next part addresses actions related to the control of the environment and of releases: water management, presentation and discussion of the main results of radiological measurements (rainfalls, air, brook waters, sediments, underground waters, radiation at the edge of the centre, ground vegetal, food chain, aquatic ecosystems), physical-chemical control of waters, actions for the protection of the environment. The report then gives an overview of the management of radioactive and conventional wastes produced by the Centre. The last part indicates and comments actions related to transparency and information (they may concern the public, local authorities, institutions, or media): visits, conferences, exhibitions, animations, partnerships, publications

  10. Paul Scherrer Institut annual report 1994. Annex IV: PSI nuclear energy and safety research progress report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Williams, T; Kallfelz, J M; Mathews, D [eds.; Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1995-10-01

    Nuclear energy research in Switzerland is concentrated at PSI. It is explicitly mentioned in the Institute`s official charter and commands about one fifth of the Institute`s federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI`s activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs.

  11. Paul Scherrer Institut annual report 1994. Annex IV: PSI nuclear energy and safety research progress report 1994

    International Nuclear Information System (INIS)

    Williams, T.; Kallfelz, J.M.; Mathews, D.

    1995-01-01

    Nuclear energy research in Switzerland is concentrated at PSI. It is explicitly mentioned in the Institute's official charter and commands about one fifth of the Institute's federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI's activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs

  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. 2015 annual report of the managing director of the CEA general and nuclear inspection for nuclear safety and radiation protection

    International Nuclear Information System (INIS)

    2016-08-01

    After an introduction by the managing director of the CEA general and nuclear inspection about activities and events of 2015, this report proposes some key figures and indicators to illustrate these activities and events. The next parts discuss, present and comment how a culture of safety is at the heart of the continuous progress approach by the CEA. The next chapters propose overviews and comments of lessons learned from nuclear inspections within the frame of audit programme or within the frame of centres' safety audits, and from reactive inspections. The last parts address the follow-up of recommendations, and progress orientations and perspectives

  14. Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-24

    This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the removal action project at the former YS-860 Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead-contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects.

  15. Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-01-01

    This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the removal action project at the former YS-860 Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead-contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects

  16. 77 FR 31493 - Eighth Coast Guard District Annual Marine Events and Safety Zones; Billy Bowlegs Pirate Festival...

    Science.gov (United States)

    2012-05-29

    ... Bowlegs Pirate Festival; Santa Rosa Sound; Ft. Walton Beach, FL AGENCY: Coast Guard, DHS. ACTION: Notice... Safety Zone for the Billy Bowlegs Pirate Festival in the Santa Rosa Sound, Ft. Walton Beach, FL on June 1... crews, vessels, and persons on navigable waters during the Billy Bowlegs Pirate Festival. During the...

  17. How Exposure Science can be Integrated into the Assessment of Ingredient Safety (American College of Toxicology Annual Meeting)

    Science.gov (United States)

    The presentation describes ongoing research in the Rapid Exposure and Dosimetry project funded under the Chemical Safety for Sustainability Research Program of the Office of Research and Development. There is a well known need for information on human exposure to thousands of che...

  18. Annual report of the Chief Executive Officer of Australian Radiation Protection And Nuclear Safety Agency, 2001-200

    International Nuclear Information System (INIS)

    2002-01-01

    In the period analysed ARPANSA contributed to the (then) Health and Aged Care portfolio's 'Outcome 1: Population Health and Safety'. The objective of this outcome was the promotion and protection of the health of all Australians and minimising the incidence of preventable mortality, illness, injury and disability. The main outcomes, as outlined in the reports are: regulation of Commonwealth activities involving radiation sources and nuclear facilities; progress towards the development of a National Directory for Radiation Protection; quality assurance programs in medical radiation and conduct evaluations of individual and population doses; health impact assessment of radiation exposure and methodologies for this assessment, recommendations and guidelines for limiting radiation exposure; progress towards third-party quality assurance certification for the personal radiation monitoring service, radionuclide analysis of gamma ray emitting nuclides, Ultraviolet Protection Factor; assessing radiopharmaceutical testing and the protection dosimeter calibration service; maintenance of a network for monitoring radionuclides in the atmosphere; safety standards and guidance in support of the work of the Radiation Health and Safety Advisory Council, the Radiation Health Committee and the Nuclear Safety Committee. The major priorities for ARPANSA in the reporting year, included the assessment of an application to construct the replacement research reactor at ANSTO, implementation of a process for public consultation and participation in the licensing of nuclear facilities and the development of national standards and codes of practice, including a standard for radiofrequency radiation

  19. Engineering task plan for the annual revision of the rotary mode core sampling system safety equipment list

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    This Engineering Task Plan addresses an effort to provide an update to the RMCS Systems 3 and 4 SEL and DCM in order to incorporate the changes to the authorization basis implemented by HNF-SD-WM-BIO-001, Rev. 0 (Draft), Addendum 5 , Safety Analysis for Rotary Mode Core Sampling. Responsibilities, task description, cost estimate, and schedule are presented

  20. 78 FR 8063 - Safety Zones; Annual Firework Displays Within the Captain of the Port, Puget Sound Area of...

    Science.gov (United States)

    2013-02-05

    ... revised to read: latitude 48[deg] 08.413' N, longitude 122[deg] 45.531' W; Tacoma Freedom Fair... received without jeopardizing the safety or security of people, places or vessels. 7. Unfunded Mandates... private sector of $100,000,000 (adjusted for inflation) or more in any one year. Though this proposed rule...

  1. ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2008. ASN annual report 2008

    International Nuclear Information System (INIS)

    2009-01-01

    ASN is an independent administrative authority tasked, on behalf of the state, with regulating nuclear safety and radiation protection in order to protect workers, patients and the environment from the hazards involved in nuclear activities. It also contributes to informing the public. ASN, run by a five-member commission, regulates the whole of the sector, acting in a completely impartial manner. The ASN Commission presents its report on the state of nuclear safety and radiation protection in France in 2008. Contents: A - Introduction: The year 2008. B - Key topics: 1. ASN actions to promote greater transparency; 2. EDF nuclear power plant ageing and operating life: the conditions for continued operation; 3. The prevention of malicious acts; 4. ASN regulation of the radiotherapy sector; 5. Regulating and monitoring the construction of the Flamanville 3 EPR reactor; 6. ASN's international nuclear safety responsibilities; 7. The new nuclear countries; 8. Decommissioning of basic nuclear installations and the low-level, long-lived waste disposal project. C - Overview: 1 - Nuclear activities: ionising radiations and health risks; 2 - Principles and stakeholders in the regulation of nuclear safety and radiation protection; 3 - Regulation; 4 - Regulation of nuclear activities and exposure to ionising radiations; 5 - Environmental protection; 6 - Public information and transparency; 7 - International relations; 8 - Radiological emergencies; 9 - Medical uses of ionising radiations; 10 - Industrial and research activities; 11 - Transport of radioactive materials; 12 - EDF nuclear power plants; 13 - Nuclear fuel cycle installations; 14 - Nuclear research facilities and various nuclear installations; 15 - Safe decommissioning of basic nuclear installations; 16 - Radioactive waste and polluted sites. D - Appendices: List of basic nuclear installations; ASN decisions and opinions published in 2008 in its Official Bulletin; Acronyms, abbreviations and names

  2. Administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, April 1, 1975. Annual report, Jan--Dec 1974

    International Nuclear Information System (INIS)

    1974-01-01

    The Secretary of Health, Education, and Welfare is required, Subpart 3, Section 2, Part F of Title III of the Public Health Service Act; 42 USC et seq. (Public Law 90-602), to submit an annual report to the President for transmittal to the Congress on or before April 1 on the adminstration of the Radiation Control for Health and Safety Act. The detailed information required to be included in the report is outlined in Section 360D of Public Law 90-602. The Food and Drug Administration, through its Bureau of Radiological Health, has been delegated the authority for the day-to-day administration of the Act. This report covers the detailed operation of the Agency in carrying out that responsibility for calendar year 1974

  3. IAEA Director General reviews state of the world's nuclear security, safety and technology at annual IAEA General Conference

    International Nuclear Information System (INIS)

    2002-01-01

    The IAEA has been unable to draw any conclusion or provide any assurance regarding Iraq's compliance with its obligations under the Security Council resolutions, it will therefore be important for the Agency to resolve, upon re-commencement of inspections, the key issue of whether the situation regarding Iraq's nuclear activities and capabilities has changed in any material way since December 1998. Regarding the status of IAEA's Safeguards Agreement with the Democratic People's Republic of Korea (DPRK) the Agency continues to be unable to verify that the DPRK has declared all the nuclear material that is subject to Agency safeguards measures under its NPT safeguards agreement. The work required to verify the correctness and completeness of the DPRK's initial declaration could take three or four years. On the issue of nuclear non-proliferation, the universalization, consolidation and strengthening of the non-proliferation regime, including concrete steps to reduce the number of and dependence on nuclear weapons, are more important than ever for the continuing sustainability and credibility of the regime. Only 27 countries had brought into force Additional Protocols agreements with the Agency, which gives the Agency increased authority to provide assurances that countries were using their nuclear actives for peaceful civilian purposes only. All countries are urged to do so. An expanded effort was needed including threat assessments to protect nuclear facilities against attack, sabotage or theft. The focus of these efforts must be expanded to cover other nuclear facilities, including research installations that also have nuclear and other radioactive material. A significant short-term priority is to bring radioactive sources under appropriate control, whether in use, storage, orphaned or in transport. Concerning global nuclear safety, it is satisfying to note that nuclear safety continues to improve at power plants worldwide. The future of nuclear power, depends on

  4. 2002 Annual report: synthesis

    International Nuclear Information System (INIS)

    2003-01-01

    This synthesis of the Annual Report 2002 presents information of the main activities on the scope of the radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 2002

  5. 2000 Annual report: synthesis

    International Nuclear Information System (INIS)

    2001-01-01

    This synthesis of the Annual Report 2000 present information of the main activities on the scope of the radiation protection and nuclear safety of the Nuclear Regulatory Authority (NRA) of the Argentina during 2000

  6. 2001 Annual report: synthesis

    International Nuclear Information System (INIS)

    2001-01-01

    This synthesis of the Annual Report 2001 presents information of the main activities on the scope of the radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 2001

  7. SAFETY

    CERN Multimedia

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  8. SAFETY

    CERN Multimedia

    C. Schaefer and N. Dupont

    2013-01-01

      “Safety is the highest priority”: this statement from CERN is endorsed by the CMS management. An interpretation of this statement may bring you to the conclusion that you should stop working in order to avoid risks. If the safety is the priority, work is not! This would be a misunderstanding and misinterpretation. One should understand that “working safely” or “operating safely” is the priority at CERN. CERN personnel are exposed to different hazards on many levels on a daily basis. However, risk analyses and assessments are done in order to limit the number and the gravity of accidents. For example, this process takes place each time you cross the road. The hazard is the moving vehicle, the stake is you and the risk might be the risk of collision between both. The same principle has to be applied during our daily work. In particular, keeping in mind the general principles of prevention defined in the late 1980s. These principles wer...

  9. Safety

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    Aspects of fission reactors are considered - control, heat removal and containment. Brief descriptions of the reactor accidents at the SL-1 reactor (1961), Windscale (1957), Browns Ferry (1975), Three Mile Island (1979) and Chernobyl (1986) are given. The idea of inherently safe reactor designs is discussed. Safety assessment is considered under the headings of preliminary hazard analysis, failure mode analysis, event trees, fault trees, common mode failure and probabalistic risk assessments. These latter can result in a series of risk distributions linked to specific groups of fault sequences and specific consequences. A frequency-consequence diagram is shown. Fatal accident incidence rates in different countries including the United Kingdom for various industries are quoted. The incidence of fatal cancers from occupational exposure to chemicals is tabulated. Human factors and the acceptability of risk are considered. (U.K.)

  10. Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-28

    This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the Lead Source Removal Project at the Former YS-86O Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. This plan covers the removal actions at the Former YS-86O Firing Ranges. These actions involve the excavation of lead-contaminated soils, the removal of the concrete trench and macadam (asphalt) paths, verification/confirmation sampling, grading and revegetation. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects.

  11. Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-01-01

    This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the Lead Source Removal Project at the Former YS-86O Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. This plan covers the removal actions at the Former YS-86O Firing Ranges. These actions involve the excavation of lead-contaminated soils, the removal of the concrete trench and macadam (asphalt) paths, verification/confirmation sampling, grading and revegetation. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects

  12. Application range affected by software failures in safety relevant instrumentation and control systems of nuclear power plants

    International Nuclear Information System (INIS)

    Jopen, Manuela; Mbonjo, Herve; Sommer, Dagmar; Ulrich, Birte

    2017-03-01

    This report presents results that have been developed within a BMUB-funded research project (Promotion Code 3614R01304). The overall objective of this project was to broaden the knowledge base of GRS regarding software failures and their impact in software-based instrumentation and control (I and C) systems. To this end, relevant definitions and terms in standards and publications (DIN, IEEE standards, IAEA standards, NUREG publications) as well as in the German safety requirements for nuclear power plants were analyzed first. In particular, it was found that the term ''software fault'' is defined differently and partly contradictory in the considered literature sources. For this reason, a definition of software fault was developed on the basis of the software life cycle of software-based I and C systems within the framework of this project, which takes into account the various aspects relevant to software faults and their related effects. It turns out that software failures result from latent faults in a software-based control system, which can lead to a non-compliant behavior of a software-based I and C system. Hereby a distinction should be made between programming faults and specification faults. In a further step, operational experience with software failures in software-based I and C systems in nuclear facilities and in nonnuclear sector was investigated. The identified events were analyzed with regard to their cause and impacts and the analysis results were summarized. Based on the developed definition of software failure and on the COMPSIS-classification scheme for events related to software based I and C systems, the COCS-classification scheme was developed to classify events from operating experience with software failures, in which the events are classified according to the criteria ''cause'', ''affected system'', ''impact'' and ''CCF potential''. This classification scheme was applied to evaluate the events identified in the framework of this project

  13. Monitoring of long-range transported air pollutants, Annual report for 1996; Overvaaking av langtransportert forurenset luft og nedboer. Atmosfaerisk tilfoersel, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Toerseth, K.; Manoe, S.

    1997-12-31

    This report describes the results from the rural air- and precipitation chemistry network in Norway. In 1996, main components in precipitation were measured at 32 sites and trace elements were determined at 13 sites. The concentrations of sulphur and nitrogen compounds in air were determined at 12 sites, and concentrations of ozone at 15 sites. The highest mean concentrations of sulphate, nitrate, ammonium and strong acid in precipitation occurred along the southern coast. Low values were found from Moere og Romsdal to Troms counties. The largest wet deposition of sulphate, nitrogen components and strong acid occurred along the coast of the southernmost tip of the country. All over the country the mean concentrations of sulphate, nitrate, ammonium and strong acid in precipitation had in general increased from 1995 to 1996. Because of small annual precipitation amounts the wet depositions were the lowest measured so far at most places in Norway. The highest content of particulate sulphate and of nitrogen components in air and in precipitation were measured in Southern Norway. The mean concentrations of sulphur dioxide were highest in Finnmark due to the nickel smelters in Russia. The largest annual mean concentrations of lead, cadmium and zinc in precipitation were measured in Southern Norway. Mercury in air decreased from 1992 to 1996 while the concentrations of lead, cadmium and zinc increased. This is opposite to the trend observed in precipitation chemistry and is probably due to emissions in Eastern Europe. 47 refs., 34 figs., 37 tabs.

  14. Mining and mining authorities in Saarland 2016. Mining economy, mining technology, occupational safety, environmental protection, statistics, mining authority activities. Annual report; Bergbau und Bergbehoerden im Saarland 2016. Bergwirtschaft, Bergtechnik, Arbeitsschutz, Umweltschutz, Statistiken, Taetigkeiten der Bergbehoerden. Jahresbericht

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-07-01

    The annual report of the Saarland Upper Mining Authority provides an insight into the activities of mining authorities. Especially, the development of the black coal mining, safety and technology of mining as well as the correlation between mining and environment are stressed.

  15. Safety and efficacy of bi-annual intra-articular LBSA0103 injections in patients with knee osteoarthritis.

    Science.gov (United States)

    Lee, Jin Kyu; Choi, Chong-Hyuk; Oh, Kwang-Jun; Kyung, Hee-Soo; Yoo, Ju-Hyung; Ha, Chul-Won; Bin, Seong-Il; Kang, Seung-Baik; Kim, Myung Ku; Lee, Ju-Hong; Lee, Myung Chul

    2017-11-01

    The objective of this study is to assess the safety and efficacy of repeated intra-articular injection of high molecular weight hyaluronic acid (LBSA0103) at a 26-week interval, in patients with osteoarthritis of the knee. The study was an open-label, single arm, multicentre prospective trial conducted in patients with symptomatic knee osteoarthritis. The intervention consisted of two intra-articular injections of LBSA0103, with the second injection performed 26 weeks after the first injection. The primary outcome was the incidence of adverse drug reactions related to each injection. Assessment of efficacy of repeated injections in terms of maintenance of pain relief was a secondary objective of this study. Of the 185 patients screened, 174 patients received the first injection and 153 patients received both injections of LBSA0103. Nine adverse drug reactions occurred in seven patients (4.02%) after the first injection, while only one adverse drug reaction occurred (0.65%) after the second injection. As a secondary outcome measure, the improvements in the efficacy parameters including total WOMAC score and weight-bearing pain were all significant at both week 13 and 39 compared to the baseline value (P injection were consistent with those after the initial injection of LBSA0103 (between week 26 and week 39, P injection of LBSA0103 at a 26-week interval is safe without increased risk of adverse drug reactions. Additionally, LBSA0103 is effective in reduction of osteoarthritis knee pain and in maintenance of pain reduction for a 39-week period when a second injection is administered.

  16. Pacific Northwest Laboratory annual report for 1982 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. Part 5. Environmental and occupational protection, assessment, and engineering

    International Nuclear Information System (INIS)

    Bair, W.J.

    1983-02-01

    Part 5 of the 1982 Annual Report to the Department of Energy's Office of Environmental Protection, Safety and Emergency Preparedness presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Programs, Office of Operational Safety, and the Office of Nuclear Safety. The report is in three sections, introduced by blue divider pages, corresponding to the program elements: Technology Impacts, Environmental and Safety Engineering, Operational and Environmental Safety. In each section, articles describe progress made during FY 1982 on individual projects, as identified by the Field Task Proposal/Agreement. Authors of these articles represent a broad spectrum of capabilities derived from various segments of the Laboratory, reflecting the interdisciplinary nature of the work

  17. Annual progress report 1981

    International Nuclear Information System (INIS)

    1982-01-01

    This annual progress report of the CEA Protection and Nuclear Safety Institut outlines a brief description of the progress made in each section of the Institut. Research activities of the Protection department include, radiation effects on man, radioecology and environment radioprotection techniques. Research activities of the Nuclear Safety department include, reactor safety analysis, fuel cycle facilities safety analysis, safety research programs. The third section deals with nuclear material security including security of facilities, security of nuclear material transport and monitoring of nuclear material management [fr

  18. Papers of the Fifth Annual Congress of the Sociedad Mexicana de Seguridad Radiologica, A.C., 2. Regional Congress on Radiological and Nuclear Safety. Vol. 2 (pt.2)

    International Nuclear Information System (INIS)

    1993-11-01

    The fulfillment of the Fifth Annual Congress of the Sociedad Mexicana de Seguridad Radiologica, A.C., this time inside the frame of the Second Regional Congress of Radiological and Nuclear Safety, is no doubt an event that approach us to make of this forum the most important for the exchange of ideas and the approaching among the members of our nuclear community. This time, the beautiful colonial city of Zacatecas, welcome us for this event, gathering fifty works in the areas of fuel cycle, power reactor operation, reactor physics, research reactors, transient analysis and instrumentation and experimental techniques. This significant number of works reaffirm the great interest of the nuclear community in to take part, presenting its most recent developments. The reporting belongs to seven of the main institutions of the country who dedicate, or are related with the technological development of the nuclear area and its different branches. With regard to participants of foreign countries, papers representing to Argentina, Brazil, Chile, United States of North America and Peru are included. The efforts of all the members of the Sociedad Mexicana de Seguridad Radiologica, A.C. has been addressed to do of the event a mean to make easy the exchange of ideas and to get acquainted with the work of other colleagues, in an ambient of warmth and surmounting. (Author)

  19. Annual report 1977

    International Nuclear Information System (INIS)

    1978-01-01

    The GKSS (Society for the Utilization of Nuclear Energy in Shipbuilding and Nautics) gives in this annual report a comprehensive survey of the research and development efforts carried out and a survey on the organisation and its sociological position. More detailed and generally explicable presentations of selected spheres of research deal this year with solid combustible neutron poisons, water desalination systems, pollution at the Elbe-mouth, trace analysis with x-ray fluor essence, heat conduction in water and under-water systems. The research and development programme is, in comparison with previous years better understandable. The range of tasks, 'utilization of nuclear energy', especially covers projects on the field of reactor safety research which were comprised in one project and fully integrated in the reactor safety programme of the Fed. Ministry for Research and Technology. Furthermore, nuclear energy ship development and works concerning working material technology are being carried out, to a smaller extent. The project of a nuclear container ship which run over a period of 5 years, was finished in 1977. Profitability calculations show that nuclear trade ships can be used in a profitable way, when the oil price has increased three-fold. This might be the case in about 15-20 years. Further plans of the GKSS on the field of nuclear energy ship development take into account this result. The range of tasks 'utilization of the sea and the shores' was comprised in a frame programme and divided in the research, fields of environment technique, water desalination, resources, and sea technique. These works are, beside reactor safety research, the main range of works of the GKSS. (orig./HK) [de

  20. 40 CFR 600.314-08 - Updating label values, annual fuel cost, Gas Guzzler Tax, and range of fuel economy for...

    Science.gov (United States)

    2010-07-01

    ... cost, Gas Guzzler Tax, and range of fuel economy for comparable automobiles. 600.314-08 Section 600.314-08 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) ENERGY POLICY FUEL ECONOMY AND CARBON-RELATED EXHAUST EMISSIONS OF MOTOR VEHICLES Fuel Economy Regulations for 1977 and Later...

  1. Proceedings of the Canadian Nuclear Society 15. annual conference

    International Nuclear Information System (INIS)

    Huynh, H.M.

    1994-01-01

    The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately

  2. Proceedings of the Canadian Nuclear Society 15. annual conference

    Energy Technology Data Exchange (ETDEWEB)

    Huynh, H M [Hydro-Quebec, Montreal, PQ (Canada)

    1994-12-31

    The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately.

  3. Safety; Avertissement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

  4. 20th annual report 2011. Convention on long-range transboundary air pollution. International cooperative programme on integrated monitoring of air pollution effects on ecosystems

    Energy Technology Data Exchange (ETDEWEB)

    Kleemola, S.; Forsius, M. (eds.)

    2011-07-01

    The Integrated Monitoring Programme (ICP IM) is part of the effect-oriented activities under the 1979 Convention on Long-range Transboundary Air Pollution, which covers the region of the United Nations Economic Commission for Europe (UNECE). The main aim of ICP IM is to provide a framework to observe and understand the complex changes occurring in natural/semi natural ecosystems. This report summarizes the work carried out by the ICP IM Programme Centre and several collaborating institutes. The emphasis of the report is in the work done during the programme year 2010/2011 including: A short summary of previous data assessments, a status report of the ICP IM activities, content of the IM database, and geographical coverage of the monitoring network, a review of published vegetation results from ICP IM and preliminary analyses of collected vegetation data, a report on updated heavy metal budgets and critical loads at ICP IM sites, report on benefits of LTER collaboration (Long Term Ecological Research network, www.lter-europe.net), National Reports on ICP IM activities are presented as annexes. (orig.)

  5. 22nd annual report 2013. Convention on long-range transboundary air pollution. International cooperative programme on integrated monitoring of air pollution effects on ecosystems

    Energy Technology Data Exchange (ETDEWEB)

    Kleemola, S.; Forsius, M. (eds.)

    2013-09-01

    The Integrated Monitoring Programme (ICP IM) is part of the effect-oriented activities under the 1979 Convention on Long-range Transboundary Air Pollution, which covers the region of the United Nations Economic Commission for Europe (UNECE). The main aim of ICP IM is to provide a framework to observe and understand the complex changes occurring in natural/semi natural ecosystems. This report summarizes the work carried out by the ICP IM Programme Centre and several collaborating institutes. The emphasis of the report is in the work done during the programme year 2012/2013 including: A short summary of previous data assessments; A status report of the ICP IM activities, content of the IM database, and geographical coverage of the monitoring network; A final report on relations between vegetation changes and nitrogen Critical Load exceedance; A progress report on base line heavy metal approach, estimation of the extent of metal turnover in European forest catchments over the last decades; A final report on sulphur and nitrogen input-output budgets at ICP IM sites in Europe; National Reports on ICP IM activities are presented as annexes.

  6. An open-label multicenter study to assess the safety of dextromethorphan/quinidine in patients with pseudobulbar affect associated with a range of underlying neurological conditions.

    Science.gov (United States)

    Pattee, Gary L; Wymer, James P; Lomen-Hoerth, Catherine; Appel, Stanley H; Formella, Andrea E; Pope, Laura E

    2014-11-01

    Pseudobulbar affect (PBA) is associated with neurological disorders or injury affecting the brain, and characterized by frequent, uncontrollable episodes of crying and/or laughing that are exaggerated or unrelated to the patient's emotional state. Clinical trials establishing dextromethorphan and quinidine (DM/Q) as PBA treatment were conducted in patients with amyotrophic lateral sclerosis (ALS) or multiple sclerosis (MS). This trial evaluated DM/Q safety in patients with PBA secondary to any neurological condition affecting the brain. To evaluate the safety and tolerability of DM/Q during long-term administration to patients with PBA associated with multiple neurological conditions. Fifty-two-week open-label study of DM/Q 30/30 mg twice daily. Safety measures included adverse events (AEs), laboratory tests, electrocardiograms (ECGs), vital signs, and physical examinations. #NCT00056524. A total of 553 PBA patients with >30 different neurological conditions enrolled; 296 (53.5%) completed. The most frequently reported treatment-related AEs (TRAEs) were nausea (11.8%), dizziness (10.5%), headache (9.9%), somnolence (7.2%), fatigue (7.1%), diarrhea (6.5%), and dry mouth (5.1%). TRAEs were mostly mild/moderate, generally transient, and consistent with previous controlled trials. Serious AEs (SAEs) were reported in 126 patients (22.8%), including 47 deaths, mostly due to ALS progression and respiratory failure. No SAEs were deemed related to DM/Q treatment by investigators. ECG results suggested no clinically meaningful effect of DM/Q on myocardial repolarization. Differences in AEs across neurological disease groups appeared consistent with the known morbidity of the primary neurological conditions. Study interpretation is limited by the small size of some disease groups, the lack of a specific efficacy measure and the use of a DM/Q dose higher than the eventually approved dose. DM/Q was generally well tolerated over this 52 week trial in patients with PBA

  7. NEA Annual Report 2016

    International Nuclear Information System (INIS)

    Magwood, William D. IV

    2017-01-01

    The Nuclear Energy Agency (NEA) is a specialised agency within the Organisation for Economic Co-operation and Development (OECD), an intergovernmental organisation of industrialised countries, based in Paris, France. The OECD is a unique forum in which its 35 member countries work together to create better policies for better lives. The objective of the NEA is to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally sound and economical use of nuclear energy for peaceful purposes. It provides authoritative assessments and forges common understandings on key issues as input to government decisions on nuclear energy policy and to broader OECD analyses in areas such as energy and the sustainable development of low-carbon economies. The NEA co-operates with a range of multilateral organisations, including the European Commission and the International Atomic Energy Agency. This 2016 annual report presents: 1 - Message from the Director-General; 2 - The Economic Challenges of Nuclear Energy; 3 - Nuclear Technology in 2016; 4 - NEA Activities by Sector: Nuclear Development; Nuclear Safety and Regulation; Human Aspects of Nuclear Safety; Radioactive Waste Management; Radiological Protection; Nuclear Science; Data Bank; Legal Affairs; 5 - General Information: Information and Communications; Organisational Structure of the NEA; NEA Publications and Brochures Produced in 2016

  8. Safety, immunogenicity and dose ranging of a new Vi-CRM₁₉₇ conjugate vaccine against typhoid fever: randomized clinical testing in healthy adults.

    Science.gov (United States)

    van Damme, Pierre; Kafeja, Froukje; Anemona, Alessandra; Basile, Venere; Hilbert, Anne Katrin; De Coster, Ilse; Rondini, Simona; Micoli, Francesca; Qasim Khan, Rana M; Marchetti, Elisa; Di Cioccio, Vito; Saul, Allan; Martin, Laura B; Podda, Audino

    2011-01-01

    Typhoid fever causes more than 21 million cases of disease and 200,000 deaths yearly worldwide, with more than 90% of the disease burden being reported from Asia. Epidemiological data show high disease incidence in young children and suggest that immunization programs should target children below two years of age: this is not possible with available vaccines. The Novartis Vaccines Institute for Global Health developed a conjugate vaccine (Vi-CRM₁₉₇) for infant vaccination concomitantly with EPI vaccines, either starting at 6 weeks with DTP or at 9 months with measles vaccine. We report the results from a Phase 1 and a Phase 2 dose ranging trial with Vi-CRM₁₉₇ in European adults. Following randomized blinded comparison of single vaccination with either Vi-CRM₁₉₇ or licensed polysaccharide vaccines (both containing 25·0 µg of Vi antigen), a randomised observer blinded dose ranging trial was performed in the same center to compare three concentrations of Vi-CRM₁₉₇ (1·25 µg, 5·0 µg and 12·5 µg of Vi antigen) with the polysaccharide vaccine. All vaccines were well tolerated. Compared to the polysaccharide vaccine, Vi-CRM₁₉₇ induced a higher incidence of mild to moderate short lasting local pain. All Vi-CRM₁₉₇ formulations induced higher Vi antibody levels compared to licensed control, with clear dose response relationship. Vi-CRM₁₉₇ did not elicit safety concerns, was highly immunogenic and is therefore suitable for further clinical testing in endemic populations of South Asia. ClinicalTrials.gov NCT01123941 NCT01193907.

  9. Safety, immunogenicity and dose ranging of a new Vi-CRM₁₉₇ conjugate vaccine against typhoid fever: randomized clinical testing in healthy adults.

    Directory of Open Access Journals (Sweden)

    Pierre van Damme

    Full Text Available Typhoid fever causes more than 21 million cases of disease and 200,000 deaths yearly worldwide, with more than 90% of the disease burden being reported from Asia. Epidemiological data show high disease incidence in young children and suggest that immunization programs should target children below two years of age: this is not possible with available vaccines. The Novartis Vaccines Institute for Global Health developed a conjugate vaccine (Vi-CRM₁₉₇ for infant vaccination concomitantly with EPI vaccines, either starting at 6 weeks with DTP or at 9 months with measles vaccine. We report the results from a Phase 1 and a Phase 2 dose ranging trial with Vi-CRM₁₉₇ in European adults.Following randomized blinded comparison of single vaccination with either Vi-CRM₁₉₇ or licensed polysaccharide vaccines (both containing 25·0 µg of Vi antigen, a randomised observer blinded dose ranging trial was performed in the same center to compare three concentrations of Vi-CRM₁₉₇ (1·25 µg, 5·0 µg and 12·5 µg of Vi antigen with the polysaccharide vaccine.All vaccines were well tolerated. Compared to the polysaccharide vaccine, Vi-CRM₁₉₇ induced a higher incidence of mild to moderate short lasting local pain. All Vi-CRM₁₉₇ formulations induced higher Vi antibody levels compared to licensed control, with clear dose response relationship.Vi-CRM₁₉₇ did not elicit safety concerns, was highly immunogenic and is therefore suitable for further clinical testing in endemic populations of South Asia.ClinicalTrials.gov NCT01123941 NCT01193907.

  10. Plutonium, americium, and uranium in blow-sand mounds of safety-shot sites at the Nevada Test Site and the Tonopah Test Range

    International Nuclear Information System (INIS)

    Essington, E.H.; Gilbert, R.O.; Wireman, D.L.; Brady, D.N.; Fowler, E.B.

    1977-01-01

    Blow-sand mounds or miniature sand dunes and mounds created by burrowing activities of animals were investigated by the Nevada Applied Ecology Group (NAEG) to determine the influence of mounds on plutonium, americium, and uranium distributions and inventories in areas of the Nevada Test Site and Tonopah Test Range. Those radioactive elements were added to the environment as a result of safety experiments of nuclear devices. Two studies were conducted. The first was to estimate the vertical distribution of americium in the blow-sand mounds and in the desert pavement surrounding the mounds. The second was to estimate the amount or concentration of the radioactive materials accumulated in the mound relative to the desert pavement. Five mound types were identified in which plutonium, americium, and uranium concentrations were measured: grass, shrub, complex, animal, and diffuse. The mount top (that portion above the surrounding land surface datum), the mound bottom (that portion below the mound to a depth of 5 cm below the surrounding land surface datum), and soil from the immediate area surrounding the mound were compared separately to determine if the radioactive elements had concentrated in the mounds. Results of the studies indicate that the mounds exhibit higher concentrations of plutonium, americium, and uranium than the immediate surrounding soil. The type of mound does not appear to have influenced the amount of the radioactive material found in the mound except for the animal mounds where the burrowing activities appear to have obliterated distribution patterns

  11. Apparent field safety of a raccoon poxvirus-vectored plague vaccine in free-ranging prairie dogs (Cynomys spp.), Colorado, USA.

    Science.gov (United States)

    Tripp, Daniel W; Rocke, Tonie E; Streich, Sean P; Abbott, Rachel C; Osorio, Jorge E; Miller, Michael W

    2015-04-01

    Prairie dogs (Cynomys spp.) suffer high rates of mortality from plague. An oral sylvatic plague vaccine using the raccoon poxvirus vector (designated RCN-F1/V307) has been developed for prairie dogs. This vaccine is incorporated into palatable bait along with rhodamine B as a biomarker. We conducted trials in August and September 2012 to demonstrate uptake and apparent safety of the RCN-F1/V307 vaccine in two prairie dog species under field conditions. Free-ranging prairie dogs and other associated small rodents readily consumed vaccine-laden baits during field trials with no apparent adverse effects; most sampled prairie dogs (90%) and associated small rodents (78%) had consumed baits. Visual counts of prairie dogs and their burrows revealed no evidence of prairie dog decline after vaccine exposure. No vaccine-related morbidity, mortality, or gross or microscopic lesions were observed. Poxviruses were not isolated from any animal sampled prior to bait distribution or on sites that received placebo baits. We isolated RCN-F1/V307 from 17 prairie dogs and two deer mice (Peromyscus maniculatus) captured on sites where vaccine-laden baits were distributed. Based on these findings, studies examining the utility and effectiveness of oral vaccination to prevent plague-induced mortality in prairie dogs and associated species are underway.

  12. Apparent field safety of a raccoon poxvirus-vectored plague vaccine in free-ranging prairie dogs (Cynomys spp.), Colorado, USA

    Science.gov (United States)

    Tripp, Daniel W.; Rocke, Tonie E.; Streich, Sean P.; Abbott, Rachel C.; Osorio, Jorge E.; Miller, Michael W.

    2015-01-01

    Prairie dogs (Cynomys spp.) suffer high rates of mortality from plague. An oral sylvatic plague vaccine using the raccoon poxvirus vector (designated RCN-F1/V307) has been developed for prairie dogs. This vaccine is incorporated into palatable bait along with rhodamine B as a biomarker. We conducted trials in August and September 2012 to demonstrate uptake and apparent safety of the RCN-F1/V307 vaccine in two prairie dog species under field conditions. Free-ranging prairie dogs and other associated small rodents readily consumed vaccine-laden baits during field trials with no apparent adverse effects; most sampled prairie dogs (90%) and associated small rodents (78%) had consumed baits. Visual counts of prairie dogs and their burrows revealed no evidence of prairie dog decline after vaccine exposure. No vaccine-related morbidity, mortality, or gross or microscopic lesions were observed. Poxviruses were not isolated from any animal sampled prior to bait distribution or on sites that received placebo baits. We isolated RCN-F1/V307 from 17 prairie dogs and two deer mice (Peromyscus maniculatus) captured on sites where vaccine-laden baits were distributed. Based on these findings, studies examining the utility and effectiveness of oral vaccination to prevent plague-induced mortality in prairie dogs and associated species are underway.

  13. Pacific Northwest Laboratory annual report for 1985 to the DOE Office of the Assistant Secretary for Environment, Safety and Health. Part 5. Overview and assessment

    International Nuclear Information System (INIS)

    Faust, L.G.

    1986-02-01

    This volume is progress on work performed for the Office of Nuclear Safety, the Office of Operational Safety, and for the Office of Environmental Analysis for each project. Separate abstracts have been prepared for individual projects. ACR

  14. 2002 Annual report

    International Nuclear Information System (INIS)

    2003-01-01

    This annual report presents information of the main activities on the scope of radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 2002. The following activities and developed topic in this report describe: radiation and nuclear safety, safeguards, physical protection, transport of radioactive materials, regulatory guides and standards, inspections, licensing, emergency systems, occupational and environmental surveillance, institutional relations with national and international organizations, training courses, information systems, human and economic resources

  15. Annual Report for 1981 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety, and Emergency Preparedness. Part 2. Ecological Sciences

    International Nuclear Information System (INIS)

    Vaughan, B.E.

    1982-02-01

    Separate abstracts were prepared for the 38 reports for this Pacific Northwest Laboratory Annual Report for 1981 to the DOE Office of Energy Research. This part dealt with research conducted in the ecological sciences

  16. Annual Report for 1981 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety, and Emergency Preparedness. Part 2. Ecological Sciences. [Lead abstract

    Energy Technology Data Exchange (ETDEWEB)

    Vaughan, B.E.

    1982-02-01

    Separate abstracts were prepared for the 38 reports for this Pacific Northwest Laboratory Annual Report for 1981 to the DOE Office of Energy Research. This part dealt with research conducted in the ecological sciences.

  17. BAM - Annual report 1975

    International Nuclear Information System (INIS)

    1976-06-01

    The annual report contains progress and activity reports of the presidential department, the departments metals and metal construction, civil engineering and building activities, organic matter, chemical safety engineering, special fields of materials testing, techniques independent of the type of material, an index, as well as general and statistic statements. (HK) [de

  18. Annual report - ENERSUL - 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The annual report of ENERSUL - Brazilian electric power distribution company - introduces the following main topics: Outlook for the State of Mato Grosso do Sul; strategic focus; financial performance; relation with investors; energy sold; capacity increases; customers; customers; energy balance; performance and quality; electric system; investments; people; human resources; synergies; awards; workplace safety; social balance; and patrimonial balance

  19. GKSS annual report 1983

    International Nuclear Information System (INIS)

    1984-01-01

    This annual report reviews the structure and activities of the GKSS in 1983. R and D work was done on reactor safety engineering, environmental research/environmental engineering and underwater technology. It also reports on cooperation with outside partners, the organization, financing, and developments in the staff structure as well as on publications, lectures, applications for patents, etc. (UA) [de

  20. PTB annual report 1985

    International Nuclear Information System (INIS)

    1986-02-01

    The annual report presents general information on the institution's activities and the various departments, and reports on scientific work in the field of metrology and safety engineering. Brief scientific accounts refer to work in the domains of mechanics and acoustics, electricity, heat, optics, industrial metrology, atomic physics, technical and scientific services, collection and disposal of radioactive waste. (DG) [de

  1. Annual Report 2004

    International Nuclear Information System (INIS)

    Swiboda, G.

    2005-01-01

    The Annual Report of the Institute of Atomic Energy describes the results of the research activities carried out in 2004. The document consist of seven parts: General Information; Operation and safety of MARIA reactor; Radiological protection and monitoring of environment; Nuclear techniques in health and environment protection and in last section the list of published in 2004 papers is presented

  2. 1985. Annual progress report

    International Nuclear Information System (INIS)

    1986-01-01

    This annual progress report of the CEA Protection and Nuclear Safety Institut outlines a description of the progress made in each sections of the Institut Research activities of the different departments include: reactor safety analysis, fuel cycle facilities analysis; and associated safety research programs (criticality, sites, transport ...), radioecology and environmental radioprotection techniques; data acquisition on radioactive waste storage sites; radiation effects on man, studies on radioprotection techniques; nuclear material security including security of facilities, security of nuclear material transport, and monitoring of nuclear material management; nuclear facility decommissioning; and finally the public information [fr

  3. Annual report and accounts 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The Annual Report of the Southern Electric Group presents the Chairman's statement, and a review by the Chief Executive which covers productivity and efficiency, VAT, subsidiaries, associated activity, energy efficiency, safety and caring for the environment. This is followed by a financial review, the director's report, and the annual accounts for the year ended 31 March 1994. (UK)

  4. 2004 annual report. Defense, safety, energy, information, health. CEA in the center of big European challenges; Rapport annuel 2004. Defense, securite, energie, information, sante. Le CEA au coeur des grands defis europeens

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is the 2004 annual report of the French atomic energy commission (CEA). It presents the R and D activities of the CEA in three main domains: 1 - defense and safety, maintaining perenniality of nuclear dissuasion and nuclear safety: supplying nuclear weapons to armies, maintaining dissuasion capability with the simulation program, sharing R and D means with the scientific community and the industrial world, designing and maintaining naval nuclear propulsion reactors, cleansing Marcoule and Pierrelatte facilities, monitoring treaties and fighting against proliferation and terrorism; 2 - energy, developing more competitive and cleaner energy sources: nuclear waste management, optimization of industrial nuclear activities, future nuclear systems and new energy technologies, basic research on energy, radiobiology and toxicology; 3 - information and health, valorizing industry thanks to technological research and supplying new tools for health and medical research: micro- and nano-technologies, software technologies, basic research for industrial innovation, nuclear technologies for health and bio-technologies. (J.S.)

  5. NEA 2015 Annual Report

    International Nuclear Information System (INIS)

    Magwood, William D. IV; Ha, Jaejoo; Nieh, Ho; Hah, Yeonhee; Siemann, Michael; Gulliford, Jim; Matsumoto, Kiyoshi; Vasquez-Maignan, Ximena; Gannon-Picot, Cynthia

    2016-01-01

    The year 2015 continued to be one of significant change, both in relation to the Agency and the global context within which it operates. As countries around the world plan aggressive nuclear power plant construction programmes, prepare to phase out and decommission plants, or to both build and retire plants simultaneously, issues of economics, waste management, public communication and nuclear safety continue to dominate the global discussion regarding nuclear power. As many countries work to absorb the outcome of the COP21 negotiations at the end of 2015, it is becoming increasingly likely that the future of nuclear power will be determined in great respect by non-traditional suppliers and new entrant countries. As reflected in this year's Annual Report, the NEA completed a significant revision of its management structure, which, it is hoped, will enable it to be more flexible, more efficient and more focused on the issues of greatest concern to its member countries. Our members provided input via the process of developing the new Strategic Plan of the Nuclear Energy Agency: 2017-2022, reaffirming their desire to maintain a sharp focus on nuclear safety as our most important mission area, while also reaffirming the vital importance of the NEA as a leading forum for technology cooperation, economic analysis and scientific investigation. In that respect, the NEA's new role as the institutional home of the International Framework for Nuclear Energy Cooperation (IFNEC) continues the Agency's coverage of complex issues associated with the deployment of new nuclear power plants. The NEA also launched the Nuclear Innovation 2050 initiative in 2015, through which NEA hopes to develop a coordinated international agenda for priority nuclear technology research and development on issues ranging from advanced fuel cycles to improved technology and methods for decommissioning retired plants. In all, 2015 was a year of both continued success for the NEA and a

  6. Range and limits of application of Sec.12, Atomic Energy Act, as a legal basis of the nuclear plant safety ordinance

    International Nuclear Information System (INIS)

    Schmidt-Preuss, Matthias

    2009-01-01

    Ensuring plant safety is a key purpose of nuclear law. Sec.7 II No.3, Atomic Energy Act, is considered the basic norm of nuclear legislation. The main requirement this embodies is ensuring 'the provisions against damage arising from construction and operation of a plant as required in accordance with the state of the art'. These normative requirements constitute the strictest yardstick existing in legislation about technology. Putting it into effect has always been the purpose of the set of nuclear rules and regulations constituting the next lower level of legislation, which so far have developed by evolution and are now to be updated comprehensively in the format of so-called modules as provided for in the concept of the Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU). So far, there has not been a nuclear plant safety ordinance. The Atomic Energy Act has always provided a basis for adopting such an ordinance, especially so in Sec.12 I 1 No.1, Atomic Energy Act. No federal government has so far wanted to make use of it. This makes it all the more remarkable that the BMU took up the subject of a nuclear plant safety ordinance as early as in 2006, starting a dialog with the federal states. This dialog meanwhile has come to a halt. The subject seems to be dormant right now, but certainly has not been shelved. Ensuring plant safety is a key purpose of nuclear law. Sec.7 II No.3, Atomic Energy Act, is considered the basic norm of nuclear legislation. The main requirement this embodies is ensuring 'the provisions against damage arising from construction and operation of a plant as required in accordance with the state of the art'. These normative requirements constitute the strictest yardstick existing in legislation about technology. Putting it into effect has always been the purpose of the set of nuclear rules and regulations constituting the next lower level of legislation, which so far have developed by evolution and are now to be

  7. CNS proceedings of the 16. annual conference, volume I and II

    International Nuclear Information System (INIS)

    Wight, A.L.; Loewer, R.

    1995-01-01

    The proceedings of the 16. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 82 papers are arranged in 16 sessions dealing with the following subjects: thermalhydraulics, containment, control and instrumentation, reactor physics, fuel channels, engineering and maintenance, safety and licensing, severe accidents and probabilistic safety assessment, new reactors and applications, radiation, fuel, computers. The individual papers have been abstracted separately

  8. CNS proceedings of the 16. annual conference, volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Wight, A L; Loewer, R [eds.

    1996-12-31

    The proceedings of the 16. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 82 papers are arranged in 16 sessions dealing with the following subjects: thermalhydraulics, containment, control and instrumentation, reactor physics, fuel channels, engineering and maintenance, safety and licensing, severe accidents and probabilistic safety assessment, new reactors and applications, radiation, fuel, computers. The individual papers have been abstracted separately.

  9. Pacific Northwest Laboratory annual report for 1979 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health, and safety

    International Nuclear Information System (INIS)

    Baalman, R.W.; Dotson, C.W.

    1980-02-01

    Part 5 of the 1979 Annual Report to the Department of Energy Assistant Secretary for the Environment presents Pacific Northwest Laboratory's progress on work performed for the Office of Technology Impacts, the Office of Environmental Compliance and Overview, and the Office of Health and Environmental Research. The report is in four sections, corresponding to the program elements: technology impacts, environmental control engineering, operational and environmental compliance, and human health studies. In each section, articles describe progress made during FY 1979 on individual projects

  10. Annual report 2001

    International Nuclear Information System (INIS)

    2002-07-01

    Article VI.J of the Agency's Statute requires the Board of Governors to submit 'an annual report to the General Conference concerning the affairs of the Agency and any projects approved by the Agency'. This report covers the period 1 January to 31 December 2001. The report outlines the IAEA activities in the following fields: nuclear power, nuclear fuel cycle and waste management technology, comparative assessment for sustainable energy development; food and agriculture, human health, marine environment and water resources, applications of physical and chemical sciences, nuclear safety, radiation safety, radioactive waste safety, co-ordination of safety activities, safeguards, security of material, verification in Iraq pursuant to UNSC resolutions, management of technical co-operation for development, policy-making, management and support

  11. Annual report 1999

    International Nuclear Information System (INIS)

    2002-01-01

    This 1999 annual report of the Authorities of Nuclear Safety presents the main technical topics of the year: time evolution of nuclear installations, crisis and particular plan of intervention, impacts of the nuclear activities on the human and the environment, the criticality risk, EdF, the EPR project, the ANDRA, transportation events and the nuclear safety at the East. It provides also information on nuclear safety, organization of nuclear safety supervision, BIN regulatory provisions, plant supervision, information of the public, international relations, emergency response, radiation protection, radioactive material transportation, radioactive waste, PWR reactors, research reactors and other installations, nuclear fuel cycle installations and final shutdown and dismantling of nuclear installations. (A.L.B.)

  12. Safety analysis and lay-out aspects of shieldings against particle radiation at the example of spallation facilities in the megawatt range

    International Nuclear Information System (INIS)

    Hanslik, R.

    2006-08-01

    This paper discusses the shielding of particle radiation from high current accelerators, spallation neutron sources and so called ADS-facilities (Accelerator Driven Systems). ADS-facilities are expected to gain importance in the future for transmutation of long-lived isotopes from fission reactors as well as for energy production. In this paper physical properties of the radiation as well as safety relevant requirements and corresponding shielding concepts are discussed. New concepts for the layout and design of such shielding are presented. Focal point of this work will be the fundamental difference between conventional fission reactor shielding and the safety relevant issues of shielding from high-energy radiation. Key point of this paper is the safety assessment of shielding issues of high current accelerators, spallation targets and ADS-blanket systems as well as neutron scattering instruments at spallation neutron sources. Safety relevant shielding requirements are presented and discussed. For the layout and design of the shielding for spallation sources computer base calculations methods are used. A discussion and comparison of the most important methods like semi-empirical, deterministic and stochastic codes are presented. Another key point within the presented paper is the discussion of shielding materials and their shielding efficiency concerning different types of radiation. The use of recycling material, as a cost efficient solution, is discussed. Based on the conducted analysis, flowcharts for a systematic layout and design of adequate shielding for targets and accelerators have been developed and are discussed in this paper. By use of these flowcharts layout and engineering design of future ADS-facilities can be performed. (orig.)

  13. Surveys of research projects concerning nuclear facility safety, financed by the Bundesminister des Innern. 9th annual report on SR-projects 1984

    International Nuclear Information System (INIS)

    1985-06-01

    The FRG's Ministry of the Interior finances studies, expertises and investigations in the field of nuclear safety. The results of such work are meant to clarify questions left open concerning the execution of licensing procedures for nuclear facilities. The GRS (Reactor Safety Company) regularly provides information on the state of such studies, on the authority of the Ministry of the Interior. Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig./HP) [de

  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. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2009. Annual report

    International Nuclear Information System (INIS)

    2010-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2009 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 and physical protection of nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations.

  16. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2008. Annual report

    International Nuclear Information System (INIS)

    Zemanova, D.; Pirozekova, M.

    2009-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2008 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 and physical protection of nuclear materials; (8) Activity of Building Office; (9) Emergency planning and preparedness; (10) International activities; (11) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations

  17. Annual Report 2006

    International Nuclear Information System (INIS)

    Swiboda, G.

    2007-01-01

    The Annual Report of the Institute of Atomic Energy describes the results of the research activities carried out in 2006. The document consist of seven parts: General Information; Operation and safety of MARIA reactor; Radiation protection and dosimetry; Nuclear Technology in Energy Generation; Solid State Physics; Nuclear techniques in Health and Environment Protection management of Hazards and in last section the list of published in 2006 papers, conferences, seminars, workshops, research projects and educational activities are presented

  18. Annual Report 2005

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

    The Annual Report of the Institute of Atomic Energy describes the results of the research activities carried out in 2005. The document consist of seven parts: General Information; Operation and safety of MARIA reactor; Radiological protection and dosimetry; Nuclear Technology in Energy Generation; Solid State Physics; Nuclear techniques in Health and Environment Protection management of Hazards and in last section the list of published in 2004 papers, conferences, seminars, workshops, research projects and educational activities are presented.

  19. Annual Report 2005

    International Nuclear Information System (INIS)

    Swiboda, G.

    2006-01-01

    The Annual Report of the Institute of Atomic Energy describes the results of the research activities carried out in 2005. The document consist of seven parts: General Information; Operation and safety of MARIA reactor; Radiological protection and dosimetry; Nuclear Technology in Energy Generation; Solid State Physics; Nuclear techniques in Health and Environment Protection management of Hazards and in last section the list of published in 2004 papers, conferences, seminars, workshops, research projects and educational activities are presented

  20. 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.

  1. 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

  2. Annual report 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This year 2000 annual report of the CEA (atomic energy commissariat) gives a general overview of the CEA activities and organization in the domains of the defence, the nuclear energy the technological research and the fundamental research. It is presented in seven main parts: contribution to national defence, civil nuclear research, technological research for the industry, pushing back the frontiers of scientific knowledge in physics and life science, mastery of installations; institute for protection and nuclear safety, research resources. (A.L.B.)

  3. Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2005. Annual report 2005

    International Nuclear Information System (INIS)

    Zemanova, D.; Seliga, M.; Sladek, V.

    2006-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2005 is presented. These activities are reported under the headings: Foreword; (1) Vision, Mission and Principles of Activities; (2) Legislation; (3) Issuance of Authorisations, Safety Assessment and Enforcement; (4) Nuclear Safety of Nuclear Installations in the Slovak Republic; (4.1) Nuclear installations in operation in the Slovak Republic; (4.2) Nuclear Installations under construction in the Slovak Republic; (4.3) Decommissioning of nuclear installations in the Slovak Republic; (5) Spent Fuel and Radioactive Waste Management and Safety of other Nuclear Installations in the Slovak Republic; (5.1) Generation and minimisation of radioactive waste; (5.2) Management of radioactive waste; (5.3) Pre-disposal management of radioactive waste; (5.4) Disposal of radioactive waste; (5.5) Shipment of radioactive waste; (5.6) Safety of other nuclear installations in the Slovak Republic; (6) Personnel Qualification and Training; (7) Nuclear Materials and Physical Protection of Nuclear installations; (8) Emergency Preparedness; (9) International Co-operation; (10) Public Communication; (11) UJD SR; (11.1) UJD SR organizational chart; (11.2) UJD SR organizational chart; (11.3) Human resources and training; (11.4) Internal system of quality assurance; (11.5) Development of UJD SR regulatory activities; Appendix: Abbreviations; Development of UJD SR regulatory activities

  4. Pacific Northwest Laboratory annual report for 1979 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health, and safety

    Energy Technology Data Exchange (ETDEWEB)

    Baalman, R.W.; Dotson, C.W. (eds.)

    1980-02-01

    Part 5 of the 1979 Annual Report to the Department of Energy Assistant Secretary for the Environment presents Pacific Northwest Laboratory's progress on work performed for the Office of Technology Impacts, the Office of Environmental Compliance and Overview, and the Office of Health and Environmental Research. The report is in four sections, corresponding to the program elements: technology impacts, environmental control engineering, operational and environmental compliance, and human health studies. In each section, articles describe progress made during FY 1979 on individual projects.

  5. 2016 Traffic Safety Culture Index

    Science.gov (United States)

    ... Newsroom SEARCH Driver Behavior & Performance 2016 Traffic Safety Culture Index This report presents the results of our annual Traffic Safety Culture Index survey, providing data on the attitudes and ...

  6. Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2006. Annual Report 2006

    International Nuclear Information System (INIS)

    Zemanova, D.; Pirozekova, M.

    2007-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2006 is presented. These activities are reported under the headings: Foreword; (1) Vision, Mission and Principles of Activities; (2) Legislation; (3) Issuance of Authorisations, Safety Assessment and Enforcement; (3.1) Issuance of Authorizations/Permissions; (3.2) Assessment and Inspections Activities; (3.3) Safety Assessment and Enforcement; (4) Nuclear Safety of Nuclear Installations in the Slovak Republic; (4.1) Nuclear installations in operation in the Slovak Republic; (4.2) Nuclear Installations under construction in the Slovak Republic; (4.3) Decommissioning of nuclear installations in the Slovak Republic; (5) Safety of Other Nuclear Installations; (5.1) Other Nuclear Installations in Operation; (5.2) Other Nuclear Installations under Construction; (5.3) Other Nuclear Installations under Decommissioning; (6) Management of Radioactive Waste; (6.1) Generation and minimisation of radioactive waste; (6.2) Management of radioactive waste; (6.3) Pre-disposal management of radioactive waste; (6.4) Disposal of radioactive waste; (6.5) Shipment of radioactive waste; (7) Nuclear Materials; (7.1) Accounting for and Control of Nuclear Materials; (7.2) Shipment of Nuclear Materials; (7.3) Illicit Trafficking of Nuclear Materials and Other Radioactive Material; (8) Emergency Planning and Preparedness; (9) International Activities; (9.1) European Affairs; (9.2) Membership in International Organisations; (9.3) Fulfilment of Obligations under International Contractual Instruments; (9.4) Bilateral Co-operation; (10) Public Communication; (11) UJD SR; (11.1) Economy Data; (11.2) Human resources and training; (11.3) Internal Management Quality System; (11.4) Development of UJD SR Regulatory Activities; (12) Abbreviations

  7. 1998 Annual report

    International Nuclear Information System (INIS)

    1999-01-01

    This annual report presents information of the main activities on the scope of the radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 1998. The activities are developed in 11 chapters and 2 appendixes, where are describing the activities and the bases of the Argentine Regulatory System. The following chapters and the appendixes are: 1.-Evolution of the nuclear regulatory activities in the Argentina. 2.-Regulatory system, laws, transport of radioactive materials, safety at the management of radioactive wastes, regulatory documents issued. 3.-Institutional relations with national and international organizations. 4.-Inspections and evaluations of the radiological and nuclear safety. 5.-Inspections and evaluations of safeguards and physical protection. 6.-Occupational surveillance. 7.-Environmental surveillance. 8.-Radiological emergencies. 9.-Scientific and technological activities. 10.-Training and technical information. 11.-Human and economic resources. Appendix 1.-Documents and regulatory licensings. Appendix 2.-Inspections to radioactive facilities

  8. Safety Checklist

    Science.gov (United States)

    1994-05-01

    given prior to issuing or renewing an OF 346? 13. Are operators’ DA Forms 348 reviewed annually for— a. Safety awards? b. Expiration of permits...place oily polishing rags or waste in covered metal cans? d. Store paint in tightly closed containers? e. Warn family members to never use gasoline...15 cream or lotion on exposed skin (face, hands, feet)? 3. Avoid extended periods of unprotected exposure to the sun? Heat cramp, heat exhaustion

  9. Administration of the Radiation Control for Health Safety Act of 1968, public law 90-602, April 1, 1984 (1983 annual report)

    International Nuclear Information System (INIS)

    1984-01-01

    The Food and Drug Administration through its National Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act. This report covers the detailed operation of the Agency in carrying out that responsibility for calendar year 1983. There are nine equipment performance or regulatory standards (television receivers, cold-cathode gas discharge tubes, microwave ovens, diagnostic x-ray systems, cabinet x-ray systems, laser products, ultrasonic therapy products, mercury vapor lamps, and sunlamp products) now in effect

  10. Annual Report 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The Institut Laue-Langevin (ILL) is an international research center using neutrons to probe the microscopic structure and dynamics of a broad range of materials. This annual report presents the ILL activities in 2000: the scientific highlights, the Millennium programme and the new developments, the workshops organized by the ILL, the experimental programme and the publications. (A.L.B.)

  11. Annual Report 2000

    International Nuclear Information System (INIS)

    2000-01-01

    The Institut Laue-Langevin (ILL) is an international research center using neutrons to probe the microscopic structure and dynamics of a broad range of materials. This annual report presents the ILL activities in 2000: the scientific highlights, the Millennium programme and the new developments, the workshops organized by the ILL, the experimental programme and the publications. (A.L.B.)

  12. Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1989. (14. annual report on SR-projects)

    International Nuclear Information System (INIS)

    1990-11-01

    Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

  13. Efficacy and safety of belimumab in patients with rheumatoid arthritis: a phase II, randomized, double-blind, placebo-controlled, dose-ranging Study.

    Science.gov (United States)

    Stohl, William; Merrill, Joan T; McKay, James D; Lisse, Jeffrey R; Zhong, Z John; Freimuth, William W; Genovese, Mark C

    2013-05-01

    To evaluate the efficacy/safety of belimumab in patients with rheumatoid arthritis (RA). Patients fulfilling American College of Rheumatology (ACR) criteria for RA for ≥ 1 year who had at least moderate disease activity while receiving stable disease-modifying antirheumatic drug (DMARD) therapy and failed ≥ 1 DMARD were randomly assigned to placebo or belimumab 1, 4, or 10 mg/kg, administered intravenously on Days 1, 14, and 28, and then every 4 weeks for 24 weeks (n = 283). This was followed by an optional 24-week extension (n = 237) in which all patients received belimumab. Primary efficacy endpoint was the Week 24 ACR20 response. Week 24 ACR20 responses with placebo and belimumab 1, 4, and 10 mg/kg were 15.9%, 34.7% (p = 0.010), 25.4% (p = 0.168), and 28.2% (p = 0.080), respectively. Patients taking any belimumab dose who continued with belimumab in the open-label extension had an ACR20 response of 41% at 48 weeks. A similar ACR20 response (42%) at 48 weeks was seen in patients taking placebo who switched in the extension to belimumab 10 mg/kg. Greater response rates were observed in patients who at baseline were rheumatoid factor-positive, anticitrullinated protein antibody-positive, or tumor necrosis factor inhibitor-naive, or had elevated C-reactive protein levels, Disease Activity Score 28 > 5.1, or low B lymphocyte stimulator levels (< 0.858 ng/ml). Adverse event rates were similar across treatment groups. In this phase II trial, belimumab demonstrated efficacy and was generally well tolerated in patients with RA who had failed previous therapies. [ClinicalTrials.gov identifier NCT00071812].

  14. 16th semi annual report

    International Nuclear Information System (INIS)

    1980-08-01

    The 16th semi-annual report 1979/2 is a description of work within the Nuclear Safety Project performed in the second six month of 1979 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics: work performed, results obtained, plans for future work. (orig.) [de

  15. Benefits to rare plants and highway safety from annual population reductions of a "native invader," white-tailed deer, in a Chicago-area woodland.

    Science.gov (United States)

    Engeman, Richard M; Guerrant, Travis; Dunn, Glen; Beckerman, Scott F; Anchor, Chris

    2014-01-01

    Overabundant white-tailed deer are one of the most serious threats to woodland plant communities in the Chicago area. Moreover, the abundant deer in a highly populated area causes economic harm and poses hazards to human safety through collisions with vehicles. The artificial conditions causing the overabundance and resulting consequences qualify the white-tailed deer in the Chicago area to be considered as "native invaders". We examined the benefits of culling deer at a Chicago-area woodland preserve by comparing browse rates on four endangered plant species from years before culling began with years with culling. We also examined deer-vehicle collision and traffic flow rates on area roads from years before culling began and years with culling to assess whether population reductions may have benefited road safety in the area. All four endangered plant species (three orchid species and sweet fern) had lower browse rates in years with culls, although the decreased browsing rates were statistically distinguishable for only two of the species (grass pink orchid and sweet fern). After first verifying that traffic flow rates did not decrease from pre-cull years to years with culls, we analyzed the Illinois Department of Transportation data from area roads based on deer-vehicle collisions causing >US$500 in damage and showed a one-third reduction in deer-vehicle collisions. An economic analysis showed a cost savings during the cull years of US$0.6 million for reducing browsing to just these four monitored plant species and the reduction in deer-vehicle collisions.

  16. Application range affected by software failures in safety relevant instrumentation and control systems of nuclear power plants; Auswirkungsbereiche von Softwarefehlern in sicherheitstechnisch wichtigen Einrichtungen von Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Jopen, Manuela; Mbonjo, Herve; Sommer, Dagmar; Ulrich, Birte

    2017-03-15

    This report presents results that have been developed within a BMUB-funded research project (Promotion Code 3614R01304). The overall objective of this project was to broaden the knowledge base of GRS regarding software failures and their impact in software-based instrumentation and control (I and C) systems. To this end, relevant definitions and terms in standards and publications (DIN, IEEE standards, IAEA standards, NUREG publications) as well as in the German safety requirements for nuclear power plants were analyzed first. In particular, it was found that the term ''software fault'' is defined differently and partly contradictory in the considered literature sources. For this reason, a definition of software fault was developed on the basis of the software life cycle of software-based I and C systems within the framework of this project, which takes into account the various aspects relevant to software faults and their related effects. It turns out that software failures result from latent faults in a software-based control system, which can lead to a non-compliant behavior of a software-based I and C system. Hereby a distinction should be made between programming faults and specification faults. In a further step, operational experience with software failures in software-based I and C systems in nuclear facilities and in nonnuclear sector was investigated. The identified events were analyzed with regard to their cause and impacts and the analysis results were summarized. Based on the developed definition of software failure and on the COMPSIS-classification scheme for events related to software based I and C systems, the COCS-classification scheme was developed to classify events from operating experience with software failures, in which the events are classified according to the criteria ''cause'', ''affected system'', ''impact'' and ''CCF potential''. This

  17. Long-range hazard assessment of volcanic ash dispersal for a Plinian eruptive scenario at Popocatépetl volcano (Mexico): implications for civil aviation safety

    Science.gov (United States)

    Bonasia, Rosanna; Scaini, Chiara; Capra, Lucia; Nathenson, Manuel; Siebe, Claus; Arana-Salinas, Lilia; Folch, Arnau

    2014-01-01

    Popocatépetl is one of Mexico's most active volcanoes threatening a densely populated area that includes Mexico City with more than 20 million inhabitants. The destructive potential of this volcano is demonstrated by its Late Pleistocene-Holocene eruptive activity, which has been characterized by recurrent Plinian eruptions of large magnitude, the last two of which destroyed human settlements in pre-Hispanic times. Popocatépetl's reawakening in 1994 produced a crisis that culminated with the evacuation of two villages on the northeastern flank of the volcano. Shortly after, a monitoring system and a civil protection contingency plan based on a hazard zone map were implemented. The current volcanic hazards map considers the potential occurrence of different volcanic phenomena, including pyroclastic density currents and lahars. However, no quantitative assessment of the tephra hazard, especially related to atmospheric dispersal, has been performed. The presence of airborne volcanic ash at low and jet-cruise atmospheric levels compromises the safety of aircraft operations and forces re-routing of aircraft to prevent encounters with volcanic ash clouds. Given the high number of important airports in the surroundings of Popocatépetl volcano and considering the potential threat posed to civil aviation in Mexico and adjacent regions in case of a Plinian eruption, a hazard assessment for tephra dispersal is required. In this work, we present the first probabilistic tephra dispersal hazard assessment for Popocatépetl volcano. We compute probabilistic hazard maps for critical thresholds of airborne ash concentrations at different flight levels, corresponding to the situation defined in Europe during 2010, and still under discussion. Tephra dispersal mode is performed using the FALL3D numerical model. Probabilistic hazard maps are built for a Plinian eruptive scenario defined on the basis of geological field data for the "Ochre Pumice" Plinian eruption (4965 14C yr BP

  18. Long-range hazard assessment of volcanic ash dispersal for a Plinian eruptive scenario at Popocatépetl volcano (Mexico): implications for civil aviation safety

    Science.gov (United States)

    Bonasia, Rosanna; Scaini, Chirara; Capra, Lucia; Nathenson, Manuel; Siebe, Claus; Arana-Salinas, Lilia; Folch, Arnau

    2013-01-01

    Popocatépetl is one of Mexico’s most active volcanoes threatening a densely populated area that includes Mexico City with more than 20 million inhabitants. The destructive potential of this volcano is demonstrated by its Late Pleistocene–Holocene eruptive activity, which has been characterized by recurrent Plinian eruptions of large magnitude, the last two of which destroyed human settlements in pre-Hispanic times. Popocatépetl’s reawakening in 1994 produced a crisis that culminated with the evacuation of two villages on the northeastern flank of the volcano. Shortly after, a monitoring system and a civil protection contingency plan based on a hazard zone map were implemented. The current volcanic hazards map considers the potential occurrence of different volcanic phenomena, including pyroclastic density currents and lahars. However, no quantitative assessment of the tephra hazard, especially related to atmospheric dispersal, has been performed. The presence of airborne volcanic ash at low and jet-cruise atmospheric levels compromises the safety of aircraft operations and forces re-routing of aircraft to prevent encounters with volcanic ash clouds. Given the high number of important airports in the surroundings of Popocatépetl volcano and considering the potential threat posed to civil aviation in Mexico and adjacent regions in case of a Plinian eruption, a hazard assessment for tephra dispersal is required. In this work, we present the first probabilistic tephra dispersal hazard assessment for Popocatépetl volcano. We compute probabilistic hazard maps for critical thresholds of airborne ash concentrations at different flight levels, corresponding to the situation defined in Europe during 2010, and still under discussion. Tephra dispersal mode is performed using the FALL3D numerical model. Probabilistic hazard maps are built for a Plinian eruptive scenario defined on the basis of geological field data for the “Ochre Pumice” Plinian eruption (4965 14C

  19. Road Safety Data, Collection, Transfer and Analysis DaCoTa. Workpackage 3, Data Warehouse: Deliverable 3.1: Annual statistical report 2010.

    NARCIS (Netherlands)

    Brandstaetter, C. Evgenikos, P. Yannis, G. Papantoniou, P. Argyropoulou E. Broughton, J. Knowles, J. Reurings, M. Vis, M. Pace, J.F. López de Cozar, E. Pérez-Fuster, P. Sanmartín J. & Haddak, M.

    2012-01-01

    The CARE database brings together the disaggregate details of road accidents and casualties across Europe, by combining the national accident databases that are maintained by all EU member states. Access to the CARE database is restricted, however, so it is important that a comprehensive range of

  20. 2003 annual report

    International Nuclear Information System (INIS)

    2004-01-01

    The 2003 issue of the annual report of the French nuclear safety authority (ASR) presents the activities of the ASR in the following domains: 2003 highlights (the project of law relative to the nuclear transparency and safety, the EPR reactor project, the radioprotection priorities, the inspection of radioprotection, the action plan for the monitoring of patients' exposure to ionizing radiations, the 2003 heat wave and the operation of nuclear power plants, the national plan of radioactive wastes management, the behaviour of long living and high level radioactive wastes, and the European 'nuclear package'), nuclear activities, ionizing radiations and health hazards, organisation of nuclear safety control and radioprotection, radioprotection and nuclear facilities regulation, control of nuclear activities, public information and transparency, international relations, radiological emergency situations, radiological and biomedical activities, industrial and research activities, transport of radioactive materials, safety and radioprotection of nuclear power plants, research and other nuclear facilities, fuel cycle centers, safety of the definitive shut-down and dismantling of nuclear facilities, radioactive waste management and cleansing of polluted sites. (J.S.)

  1. Annual report and accounts 1992

    International Nuclear Information System (INIS)

    1992-01-01

    Amersham International, the health science company presents here its Annual Report and accounts for the year 1991 to 1992. Concentrating on developments in life science research, nuclear healthcare and industrial quality and safety assurance, Amersham International has undergone major restructuring this year in order to focus its scientific, financial and managerial resources on the application of radioactivity to detection and measurement. (UK)

  2. 2000 Annual report

    International Nuclear Information System (INIS)

    2001-01-01

    This annual report presents information of the main activities on the scope of radiation protection and nuclear safety of the Nuclear Regulatory Authority (NRA) of the Argentina during 2000. The following activities and developed topic in this report describe: the Argentine regulatory system; the evolution of the nuclear regulatory activities in the Argentina since the beginnings in the National Atomic Energy Commission (NAEC) of Argentina; the nuclear regulatory laws and standards; the safeguards and inspection of the nuclear facilities and nuclear power plants; the radiological emergency systems; the environmental monitoring; the institutional relations with national and international organizations; the biological and physics dosimetry; the training courses and meetings; the economic and human recourses

  3. CEA Annual report 2007

    International Nuclear Information System (INIS)

    2007-01-01

    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.)

  4. 1996 annual report

    International Nuclear Information System (INIS)

    1996-01-01

    This 1996 issue of the annual report of the French Commissariat a l'Energie Atomique (CEA) gives a general overview of CEA organization, activities, human resources, international relations and external communication with some budgetary informations. The main activities described concern the national defence, the fuel cycle, the nuclear reactors, the condensed matter and life sciences, the advanced technologies, the protection and transfer of knowledge and technologies, the environmental activities, the management and processing of nuclear wastes, the nuclear protection and safety, the technical and scientific information, the teaching and training, the scientific prizes, the committees, councils and commissions. (J.S.)

  5. Institute annual report 2004

    International Nuclear Information System (INIS)

    2005-01-01

    The mission of the ITU (Institute for Transuranium Elements) is to protect the European citizen against risk associated with the handling and storage of highly radioactive elements. The JRC (Joint Research Center) provide customer-driven scientific and technical support for the conception, development, implementation and monitoring of EU policies. In this framework this annual report presents the TU actions in: basic actinide research, spent fuel characterization, safety of nuclear fuels, partitioning and transmutation, alpha-immunotherapy/radiobiology, measurement of radioactivity in the environment, safeguards research and development. (A.L.B.)

  6. 1997 annual report

    International Nuclear Information System (INIS)

    1997-01-01

    This 1997 issue of the annual report of the French Commissariat a l'Energie Atomique (CEA) gives a general overview of the CEA organization, activities, human resources, international relations and communication with some budgetary information. The main activities described concern the national defence, the fuel cycle, the nuclear reactors, the nuclear protection and safety, the advanced technologies, the quasi-particles, the effects of ionizing radiations on humans, the medical imagery, the transfer of technology, the protection and valorization of knowledge, the radioactive wastes and spent fuels management, the training and teaching, the scientific prizes, the committees, councils and commissions. (O.M.)

  7. Annual report 2002

    International Nuclear Information System (INIS)

    2003-01-01

    This annual report presents the CEA (Atomic Energy Research Center) activities and research programs during the year 2002. the first part is devoted to the scientific development in the defense, nuclear energy, technology, fundamental research and valuation domains. The second and third parts present respectively the development conditions with the environment safety and the means of development with the human resources, the information technology, the training and the public relations. The fourth part situates the Cea enterprise in the economy and the fifth part the Cea development in the Europe and the world. The last part is the financial accounting. (A.L.B.)

  8. Annual Report 2011

    International Nuclear Information System (INIS)

    2011-01-01

    The PNRI Annual Report summarizes the institute's yearly progress in nuclear research and development projects, services, regulations, technology transfers and information dissemination on the peaceful applications of nuclear science and technology. The establishment and future operation of the Technetium 99m Generator Facility and the Electron Beam Facility will enhance the institute's capabilities. The PNRI has made great strides in agricultural and environmental research, helping to improve crop growth and water resource management. It served more clients availing of irradiation and other services, and was vigilant in monitoring incidents in the Southeast Asian region to preserve national nuclear safety and security

  9. Institute annual report 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The mission of the ITU (Institute for Transuranium Elements) is to protect the European citizen against risk associated with the handling and storage of highly radioactive elements. The JRC (Joint Research Center) provide customer-driven scientific and technical support for the conception, development, implementation and monitoring of EU policies. In this framework this annual report presents the TU actions in: basic actinide research, spent fuel characterization, safety of nuclear fuels, partitioning and transmutation, alpha-immunotherapy/radiobiology, measurement of radioactivity in the environment, safeguards research and development. (A.L.B.)

  10. TOTAL annual report 2003

    International Nuclear Information System (INIS)

    2004-01-01

    This 2003 annual report of the Group Total provides economical results and information of the society on the following topics: keys data, the corporate governance (Directors charter, board of directors, audit committee, nomination and remuneration committee, internal control procedures, compensation of directors and executive officers), the corporate social responsibility (environmental stewardship, the future of energy management, the safety enhancement, the human resources, ethics and local development), the investor relations, the management report, the upstream exploration and production, the downstream refining, marketing, trading and shipping, the chemicals and financial and legal information. (A.L.B.)

  11. GKSS annual report 1987

    International Nuclear Information System (INIS)

    1988-01-01

    GKSS-Forschungszentrum Geesthacht GmbH, one of the national research centers, carries out R and D work on conservation of resources and environment, improvement of working conditions and on increase of economic competitiveness. The activities fall into the fields energy research and technology, basic technologies, marine research and techniques, health-environment-biotechnology. The annual report contains selected research work in summaries, the report on R and D work in reactor safety, materials research, environmental and climate research as well as environmental, and underwater techniques, describes the research institutes, cooperation with external partners, the organization, the budget, personnel, publications, including patent applications, and lectures. (HK) [de

  12. Annual report 1987-1988

    International Nuclear Information System (INIS)

    1988-01-01

    This First Annual Report of the Safety Review Committee describes the Committee's operations for the year ending 30 June 1988. The Committee was established on 27 April 1987 in accordance with Section 26 of the Australian Nuclear Science and Technology Organisation (ANSTO) Act. The report provides an overview of ANSTO's Lucas Heights site, its facilities and resources and the potential of its operations for off-site consequences. The safety of the HIFAR and MOATA reactors, the HIFAR refurbishing program, the management of radioactive wastes, and occupational health and safety are discussed as well as the regulatory environment in which ANSTO operates

  13. Quantifying reactor safety margins: Application of CSAU [Code Scalability, Applicability and Uncertainty] methodology to LBLOCA: Part 3, Assessment and ranging of parameters for the uncertainty analysis of LBLOCA codes

    International Nuclear Information System (INIS)

    Wulff, W.; Boyack, B.E.; Duffey, R.B.

    1988-01-01

    Comparisons of results from TRAC-PF1/MOD1 code calculations with measurements from Separate Effects Tests, and published experimental data for modeling parameters have been used to determine the uncertainty ranges of code input and modeling parameters which dominate the uncertainty in predicting the Peak Clad Temperature for a postulated Large Break Loss of Coolant Accident (LBLOCA) in a four-loop Westinghouse Pressurized Water Reactor. The uncertainty ranges are used for a detailed statistical analysis to calculate the probability distribution function for the TRAC code-predicted Peak Clad Temperature, as is described in an attendant paper. Measurements from Separate Effects Tests and Integral Effects Tests have been compared with results from corresponding TRAC-PF1/MOD1 code calculations to determine globally the total uncertainty in predicting the Peak Clad Temperature for LBLOCAs. This determination is in support of the detailed statistical analysis mentioned above. The analyses presented here account for uncertainties in input parameters, in modeling and scaling, in computing and in measurements. The analyses are an important part of the work needed to implement the Code Scalability, Applicability and Uncertainty (CSAU) methodology. CSAU is needed to determine the suitability of a computer code for reactor safety analyses and the uncertainty in computer predictions. The results presented here are used to estimate the safety margin of a particular nuclear reactor power plant for a postulated accident. 25 refs., 10 figs., 11 tabs

  14. 2013 NEA Annual Report

    International Nuclear Information System (INIS)

    2014-01-01

    concerned with nuclear and radiation safety issues: the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH). However, the follow-up to Fukushima continues to involve all areas of the Agency's work, as member countries look to implement practical measures and improvements based on lessons learnt. The NEA will continue to offer its direct assistance to the Japanese authorities in addressing remaining significant challenges, including environmental remediation and recovery, the management of radioactive waste and the decommissioning of the Fukushima Daiichi reactors. This Annual Report provides an overview of NEA activities for 2013, ranging from specific follow-up to the Fukushima Daiichi accident to further work in the areas of nuclear safety and regulation, radioactive waste management, radiological protection, nuclear science, nuclear law and nuclear energy development and the fuel cycle. While it is clear that Fukushima has had a profound effect on the nuclear energy sector, its development is set to continue in the coming years. Reflecting the need for secure supplies of low-carbon electricity, the use of nuclear power is projected to increase in a number of countries, notably in those that are seeking to diversify their energy mixes and to respond to global climate change objectives. The decision to introduce or to further develop the use of nuclear energy is an important one, which requires robust legal and regulatory frameworks and, first and foremost, an absolute commitment to safety. Table of contents: I. Message from the Director-General; II. The Fukushima Daiichi Accident and NEA Follow-up; III. Nuclear Power in 2013; IV. Technical Programmes: Nuclear Development and the Fuel Cycle, Nuclear Safety and Regulation, Radioactive Waste Management, Radiological Protection, Nuclear Science, Data Bank, Legal Affairs, Joint Projects and Other Co

  15. 1999 Annual Report

    International Nuclear Information System (INIS)

    1999-01-01

    This annual report presents information on the main activities carried out by the Nuclear Regulatory Authority (ARN) of Argentina during 1999, on radiation protection and nuclear safety. The work is developed in 9 chapters, 1 summary and 2 appendixes, where a description of the following activities and the bases of the Argentina Regulatory Systems are given: 1. Evolution of the nuclear regulatory activities in Argentina. Organic structures, tasks and budget. 2. Regulatory system, laws, transport of radioactive materials, safety at the management of radioactive wastes, regulatory documents issued. 3. Institutional relations with national and international organizations. 4. Inspection and evaluations of nuclear installations. Safeguards and physical protection. 5. Occupational and environmental surveillance. 6. Radiological emergencies. 7. Scientific and technological activities. Nuclear Regulatory Authority's laboratories. 8. Training, technical information and software development. 9. Radioactive facilities inspections

  16. GKSS annual report 1980

    International Nuclear Information System (INIS)

    1981-01-01

    This annual report of the GKSS-Research Centre Geesthacht GmbH contains a survey of the research- and development work done in the year of the report and a survey on the organisation and situation of the society. The R and D programme can be divided in two parts: utilization of nuclear energy; utilization of the sea and the coasts. The first part concerns tasks on the sector of reactor safety compiled to a project which is fully integrated into the programme Reactor Safety of the Federal Ministy for Research and Technology. Development of nuclear-energy propelled vessels is continued to a smaller extent than before. The NS OTTO HAHN stopped operations in 1979. In 1980 a waste-disposed concept for the nuclear waste was developed, on the basis of which the GKSS received permission to put the ship out of service. (orig./RW) [de

  17. 2004 Annual report

    International Nuclear Information System (INIS)

    2005-01-01

    This annual report presents information of the main activities on the scope of radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 2004. The main topics are the regulatory framework, the national systems to supervise nuclear installations, the emergency systems, the environmental control, the laboratories of the ARN, the institutional relations and the non-proliferation, the training and the public information, the radiological and the nuclear safety inspections, the safeguards and the physical protection, the quality assurance in the ARN, the environmental monitoring, and the human and economic resources. Also, this publication has four annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; ethical code; measurements and evaluations of the drinking water in Ezeiza (Argentina)

  18. GKSS annual report 1990

    International Nuclear Information System (INIS)

    1991-01-01

    The GKSS-Forschungszentrum at Geesthacht, as one of the larger research institutions in the Federal Republic of Germany, contributes through its R and D studies to the objectives of the Federal Government's research and technology policies. The program for 1990 was divided according to the following main research topics: Materials research; environmental research, climate research; environmental technology; under-water technology; reactor safety research. The first three topics are areas of study suitable for long-term work and for extension if possible. All studies on reactor safety research have been concluded in the last few years, except for one project. The annual report contains a summary of the R and D studies carried out in the reporting year, as well as a survey of the company's organization and situation. These sections are preceded by articles on selected research studies. (BBR) [de

  19. Annual report on the administration of the Radiation Control for health and Safety Act of 1968, Public Law 90-602, April 1, 1991. Rept. for Jan-Dec 90

    International Nuclear Information System (INIS)

    1991-01-01

    The Secretary of Health and Human Services is required by Subpart 3, Part F of Title III of the Public Health Service Act; 42 USC 263b et seq. (Public Law 90-602) to submit an annual report to the President for transmittal to the Congress on or before April 1 on the administration of the Radiation Control for Health and Safety Act. The detailed information required in the report is outlined in Section 360D of the Public Health Service Act. The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1990. In reviewing the operations of the Center for Devices and Radiological Health as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report). Manufacturers of electronic products are required by 21 CFR 1002.20 to report accidental radiation occurrences to the Center for Devices and Radiological Health. The Center no longer maintains a Radiation Incidents Registry, since accidental radiation occurrences are reported through the Device Experience Network (DEN) and through the requirements of the Medical Device Reporting (MDR) Regulations

  20. Underwater Ranging

    OpenAIRE

    S. P. Gaba

    1984-01-01

    The paper deals with underwater laser ranging system, its principle of operation and maximum depth capability. The sources of external noise and methods to improve signal-to-noise ratio are also discussed.