WorldWideScience

Sample records for safety statistics annual

  1. 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...

  2. 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...

  3. Annual Statistical Supplement, 2002

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2002 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  4. Annual Statistical Supplement, 2010

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2010 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  5. Annual Statistical Supplement, 2007

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2007 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  6. Annual Statistical Supplement, 2001

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2001 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  7. Annual Statistical Supplement, 2016

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2016 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  8. Annual Statistical Supplement, 2011

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2011 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  9. Annual Statistical Supplement, 2005

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2005 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  10. Annual Statistical Supplement, 2015

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2015 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  11. Annual Statistical Supplement, 2003

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2003 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  12. Annual Statistical Supplement, 2017

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2017 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  13. Annual Statistical Supplement, 2008

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2008 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  14. Annual Statistical Supplement, 2014

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2014 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  15. Annual Statistical Supplement, 2004

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2004 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  16. Annual Statistical Supplement, 2000

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2000 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  17. Annual Statistical Supplement, 2009

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2009 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  18. Annual Statistical Supplement, 2006

    Data.gov (United States)

    Social Security Administration — The Annual Statistical Supplement, 2006 includes the most comprehensive data available on the Social Security and Supplemental Security Income programs. More than...

  19. 2017 Annual Disability Statistics Supplement

    Science.gov (United States)

    Lauer, E. A; Houtenville, A. J.

    2018-01-01

    The "Annual Disability Statistics Supplement" is a companion report to the "Annual Disability Statistics Compendium." The "Supplement" presents statistics on the same topics as the "Compendium," with additional categorizations by demographic characteristics including age, gender and race/ethnicity. In…

  20. 2017 Annual Disability Statistics Compendium

    Science.gov (United States)

    Lauer, E. A.; Houtenville, A. J.

    2018-01-01

    The "Annual Disability Statistics Compendium" and its compliment, the "Annual Disability Statistics Supplement," are publications of statistics about people with disabilities and about the government programs which serve them. The "Compendium" and "Supplement" are designed to serve as a summary of government…

  1. Transportation statistics annual report 2010

    Science.gov (United States)

    2011-01-01

    The Transportation Statistics Annual Report (TSAR) presents data and information compiled by the Bureau of Transportation Statistics (BTS), a component of the U.S. Department of Transportations (USDOTs) Research and Innovative Technology Admini...

  2. Transportation statistics annual report 2009

    Science.gov (United States)

    2009-01-01

    The Transportation Statistics Annual Report (TSAR) presents data and information selected by the Bureau of Transportation Statistics (BTS), a component of the U.S. Department of Transportation's (USDOT's) Research and Innovative Technology Administra...

  3. Transportation Statistics Annual Report, 2017

    Science.gov (United States)

    2018-01-01

    The Transportation Statistics Annual Report describes the Nations transportation system, the systems performance, its contributions to the economy, and its effects on people and the environment. This 22nd edition of the report is based on infor...

  4. Transportation statistics annual report, 2015

    Science.gov (United States)

    2016-01-01

    The Transportation Statistics Annual Report : describes the Nations transportation system, : the systems performance, its contributions to : the economy, and its effects on people and the : environment. This 20th edition of the report is : base...

  5. Transportation statistics annual report, 2013

    Science.gov (United States)

    2014-01-01

    The Transportation Statistics Annual Report : describes the Nations transportation system, : the systems performance, its contributions to : the economy, and its effects on people and the : environment. This 18th edition of the report is : base...

  6. Transportation Statistics Annual Report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Fenn, M.

    1997-01-01

    This document is the fourth Transportation Statistics Annual Report (TSAR) prepared by the Bureau of Transportation Statistics (BTS) for the President and Congress. As in previous years, it reports on the state of U.S. transportation system at two levels. First, in Part I, it provides a statistical and interpretive survey of the system—its physical characteristics, its economic attributes, aspects of its use and performance, and the scale and severity of unintended consequences of transportation, such as fatalities and injuries, oil import dependency, and environment impacts. Part I also explores the state of transportation statistics, and new needs of the rapidly changing world of transportation. Second, Part II of the report, as in prior years, explores in detail the performance of the U.S. transportation system from the perspective of desired social outcomes or strategic goals. This year, the performance aspect of transportation chosen for thematic treatment is “Mobility and Access,” which complements past TSAR theme sections on “The Economic Performance of Transportation” (1995) and “Transportation and the Environment” (1996). Mobility and access are at the heart of the transportation system’s performance from the user’s perspective. In what ways and to what extent does the geographic freedom provided by transportation enhance personal fulfillment of the nation’s residents and contribute to economic advancement of people and businesses? This broad question underlies many of the topics examined in Part II: What is the current level of personal mobility in the United States, and how does it vary by sex, age, income level, urban or rural location, and over time? What factors explain variations? Has transportation helped improve people’s access to work, shopping, recreational facilities, and medical services, and in what ways and in what locations? How have barriers, such as age, disabilities, or lack of an automobile, affected these

  7. Youth Sports Safety Statistics

    Science.gov (United States)

    ... 6):794-799. 31 American Heart Association. CPR statistics. www.heart.org/HEARTORG/CPRAndECC/WhatisCPR/CPRFactsandStats/CPRpercent20Statistics_ ... Mental Health Services Administration, Center for Behavioral Health Statistics and Quality. (January 10, 2013). The DAWN Report: ...

  8. 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.)

  9. 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.

  10. Statistical considerations on safety analysis

    International Nuclear Information System (INIS)

    Pal, L.; Makai, M.

    2004-01-01

    The authors have investigated the statistical methods applied to safety analysis of nuclear reactors and arrived at alarming conclusions: a series of calculations with the generally appreciated safety code ATHLET were carried out to ascertain the stability of the results against input uncertainties in a simple experimental situation. Scrutinizing those calculations, we came to the conclusion that the ATHLET results may exhibit chaotic behavior. A further conclusion is that the technological limits are incorrectly set when the output variables are correlated. Another formerly unnoticed conclusion of the previous ATHLET calculations that certain innocent looking parameters (like wall roughness factor, the number of bubbles per unit volume, the number of droplets per unit volume) can influence considerably such output parameters as water levels. The authors are concerned with the statistical foundation of present day safety analysis practices and can only hope that their own misjudgment will be dispelled. Until then, the authors suggest applying correct statistical methods in safety analysis even if it makes the analysis more expensive. It would be desirable to continue exploring the role of internal parameters (wall roughness factor, steam-water surface in thermal hydraulics codes, homogenization methods in neutronics codes) in system safety codes and to study their effects on the analysis. In the validation and verification process of a code one carries out a series of computations. The input data are not precisely determined because measured data have an error, calculated data are often obtained from a more or less accurate model. Some users of large codes are content with comparing the nominal output obtained from the nominal input, whereas all the possible inputs should be taken into account when judging safety. At the same time, any statement concerning safety must be aleatory, and its merit can be judged only when the probability is known with which the

  11. 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)

  12. 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)

  13. 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.

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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.)

  20. 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)

  1. 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.)

  2. 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...

  3. 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)

  4. 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.

  5. Alberta oil and gas industry : annual statistics for 1997

    International Nuclear Information System (INIS)

    1998-01-01

    Alberta's 1997 annual and historical statistics for the supply and disposition of the following oil and gas products was presented: (1) crude oil and equivalent, (2) gas, (3) ethane, (4) propane, (5) butanes, (6) NGL mixes, and (7) sulphur. Statistics regarding the deliveries and average price of the products, and a statistical summary of well drilling activities in the province were also provided. tabs

  6. Alberta oil and gas industry : annual statistics for 1996

    International Nuclear Information System (INIS)

    1997-01-01

    Alberta's 1996 annual and historical statistics for the supply and disposition of the following oil and gas products was presented: (1) crude oil and equivalent, (2) natural gas, (3) ethane, (4) propane, (5) butanes, (6) natural gas liquids, and (7) sulphur. Statistics regarding the deliveries and average price of the products and statistical data on drilling activity during 1996 were also included. Tables

  7. 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

  8. Alberta electric industry annual statistics for 1998

    International Nuclear Information System (INIS)

    1999-06-01

    Tables containing data on electric energy generation and capacity for Alberta are provided for the following aspects: capacity and generation of power plants for 1998; capacity of power plants by type, unit, and energy resource for 1998; generating units approved for construction for 1998; generating units completed in 1998; transmission additions approved for construction and completed for 1998; net annual generating capacity and generation for 1988-1998; net monthly generation by plant for 1998; net annual generation by energy resource and type for 1988-1998; net monthly generation by energy resource and type for 1998; generation capacity reserve; relative capacity and generation by type of energy resource for 1998; capacity, generation and fuel consumption of isolated plants for 1998; other industrial on-site plant capacity and generation for 1998. Also listed are: energy resource consumption and energy conversion efficiency of thermal power plants for 1998; stack emissions from thermal generating plants for 1998; non-utility electric generators, wind and hydro for 1998; and hydroelectric energy utilization and conversion efficiency for 1998. Tables contain information on electric energy generation and capacity for hydroelectric energy stored in reservoirs in 1998; details of non-coincident net peak generation and load by utility operators for the Alberta electric system for 1998; and Alberta electric system generation and load at peak load hour for 1998. Further tables cover electric energy distribution for interchange and distribution for 1998 and 1981-1998; annual energy distribution to ultimate customers for 1988-1998 and to ultimate customers for 1998; and the number of electric utility customers in 1998. Final tables cover the transmission and distribution systems with data on: circuit km of such lines for 1988-1998; total circuit km of such lines by major electric utility for 1998 and number of rural electric utility customers for 1998

  9. 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)

  10. 34 CFR 668.49 - Institutional fire safety policies and fire statistics.

    Science.gov (United States)

    2010-07-01

    ... 34 Education 3 2010-07-01 2010-07-01 false Institutional fire safety policies and fire statistics... fire statistics. (a) Additional definitions that apply to this section. Cause of fire: The factor or...; however, it does not include indirect loss, such as business interruption. (b) Annual fire safety report...

  11. Statistical aspects of food safety sampling

    NARCIS (Netherlands)

    Jongenburger, I.; Besten, den H.M.W.; Zwietering, M.H.

    2015-01-01

    In food safety management, sampling is an important tool for verifying control. Sampling by nature is a stochastic process. However, uncertainty regarding results is made even greater by the uneven distribution of microorganisms in a batch of food. This article reviews statistical aspects of

  12. 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

  13. Annual summary of vital statistics: 2005.

    Science.gov (United States)

    Hamilton, Brady E; Miniño, Arialdi M; Martin, Joyce A; Kochanek, Kenneth D; Strobino, Donna M; Guyer, Bernard

    2007-02-01

    The general fertility rate in 2005 was 66.7 births per 1000 women aged 15 to 44 years, the highest level since 1993. The birth rate for teen mothers (aged 15 to 19 years) declined by 2% between 2004 and 2005, falling to 40.4 births per 1000 women, the lowest ever recorded in the 65 years for which there are consistent data. The birth rates for women > or = 30 years of age rose in 2005 to levels not seen in almost 40 years. Childbearing by unmarried women also increased to historic record levels for the United States in 2005. The cesarean-delivery rate rose by 4% in 2005 to 30.2% of all births, another record high. The preterm birth rate continued to rise (to 12.7% in 2005), as did the rate for low birth weight births (8.2%). The infant mortality rate was 6.79 infant deaths per 1000 live births in 2004, not statistically different from the rate in 2003. Pronounced differences in infant mortality rates by race and Hispanic origin continue, with non-Hispanic black newborns more than twice as likely as non-Hispanic white and Hispanic infants to die within 1 year of birth. The expectation of life at birth reached a record high in 2004 of 77.8 years for all gender and race groups combined. Death rates in the United States continued to decline, with death rates decreasing for 9 of the 15 leading causes. The crude death rate for children aged 1 to 19 years did not decrease significantly between 2003 and 2004. Of the 10 leading causes of death for 2004 in this age group, only the rates for influenza and pneumonia showed a significant decrease. The death rates increased for intentional self-harm (suicide), whereas rates for other causes did not change significantly for children. A large proportion of childhood deaths continue to occur as a result of preventable injuries.

  14. Statistical modelling of traffic safety development

    DEFF Research Database (Denmark)

    Christens, Peter

    2004-01-01

    there were 6861 injury trafficc accidents reported by the police, resulting in 4519 minor injuries, 3946 serious injuries, and 431 fatalities. The general purpose of the research was to improve the insight into aggregated road safety methodology in Denmark. The aim was to analyse advanced statistical methods......, that were designed to study developments over time, including effects of interventions. This aim has been achieved by investigating variations in aggregated Danish traffic accident series and by applying state of the art methodologies to specific case studies. The thesis comprises an introduction...

  15. Alberta oil and gas industry: annual statistics for 1995

    International Nuclear Information System (INIS)

    1996-01-01

    Statistical data for 1995 concerning the supply and disposition of crude oil and equivalent, natural gas, ethane, butanes, natural gas liquids, and sulphur in the Province of Alberta, were provided. A list of new wells drilled during 1995, and an annual well count, were also included

  16. Alberta oil and gas industry: Annual statistics for 1997. Statistical series number 98-17

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents annual statistics for the Alberta oil and gas industry for the supply and disposition of crude oil and equivalent; gas; ethane; propane; butanes; NGL mixes; and sulfur. Figures are given for deliveries and prices for the current year and also historically (1987--1996). Figures are also provided for the number of wells drilled during the year, meters drilled, and the annual well count

  17. Alberta oil and gas industry annual statistics for 1999

    International Nuclear Information System (INIS)

    2000-01-01

    A compilation of statistical data from Alberta's oil and gas industry was presented to provide energy analysts and economists a single source of consistent energy-related data. Alberta is Canada's largest crude oil and natural gas producer. This report provides current monthly and historical annual energy data covering the last decade. Data is organized by energy type including butane, ethane, natural gas, natural gas liquids, oil, propane and sulphur. This CD-Rom also included statistical data on energy supply, energy production, disposition, and prices. tabs

  18. 9th Annual UNCG Regional Mathematics and Statistics Conference

    CERN Document Server

    Chhetri, Maya; Gupta, Sat; Shivaji, Ratnasingham

    2015-01-01

    This volume contains rigorously reviewed papers on the topics presented by students at The 9th Annual University of North Carolina at Greensboro Regional Mathematics and Statistics Conference (UNCG RMSC) that took place on November 2, 2013.  All papers are coauthored by student researchers and their faculty mentors. This conference series was inaugurated in 2005, and it now attracts over 150 participants from over 30 universities from North Carolina and surrounding states. The conference is specifically tailored for students to present their research projects that encompass a broad spectrum of topics in mathematics, mathematical biology, statistics, and computer science.

  19. 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.

  20. 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.)

  1. 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 ...

  2. Annual statistical information 1996; Informe estatistico anual 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This annual statistical report aims to propagate the information about the generation, transmission and distribution systems evolution and about the electric power market from the Parana State, Brazil, in 1996. The electric power consumption in the distribution area of the Parana Power Company (COPEL) presented a growth about 6,7%. The electric power production in the the COPEL plants increased 42,2% higher than 1995, due to the outflows verified in the Iguacu river and to the long period of the affluence reduction that the Southern region tanks coursed during this year. This report presents statistical data about the following topics: a) electric power energy balance from the Parana State; b) electric power energy balance from the COPEL - own generation, certain interchange, electric power requirement, direct distribution and the electric system 6 graphs, 3 maps, 61 tabs.; e-mail: splcnmr at mail.copel.br

  3. 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.

  4. 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)

  5. 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)

  6. 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...

  7. 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...

  8. 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)

  9. 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

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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)

  3. Annual Training: Leader’s Safety Guide

    Science.gov (United States)

    1991-10-01

    QiSTsreUTFOH STATEMENT X; DISTIUaimON AUTHORIZED TOL’S GOVSRNMES’T ÄGSNCES »ND ’(WATE INDIVIDUALS OR ENTERPRISES E.UÖ3SLE TO OBTAIN ESPORT ...Statistics show that— • In World War II, one out of every five American soldiers killed died as a result of an accident. • In Korea , more than half

  4. The Research Contract Programme annual report and statistics for 2000

    International Nuclear Information System (INIS)

    2001-06-01

    53 Coordinated Research Projects (CRPs) were completed in 2000. 38 of these CRPs concerned topics in Nuclear Sciences and Applications and 15 were related to nuclear energy and safety. These CRPs were funded for $9,275,648; the average annual cost per CRP was $38,892. A list of these CRPs is included. Evaluations of these CRPs will be completed by the end of 2001 and included in the next annual report. The Agency's unique position as a technical international organization has enabled it to act as an international platform to lead groups of nuclear scientists by co-ordinating research and developmental activities addressing important problems in Member States. CRPs have been used to transfer existing technologies to developing countries, as well as for the development of new technologies in those countries. Since CRPs are tailored to finding solutions to specific problems, as compared to general techniques, their potential value in terms of the effect on Member States' level of development is substantial. In an effort to further enhance the effectiveness of CRPs developed and coordinated by the Agency, various initiatives have been suggested and the Research Contract Programme has been the subject of several advisory fora. The PPAS of Major Programme 2, the Senior Evaluation Group (SEG), and an internal audit of the programme have recently made recommendations to this end. Based on these reviews, the Agency has begun to fund fewer, but better focused and more substantially funded CRPs. Whereas in 1999, the Agency was carrying out 159 CRPs, 132 CRPs were carried out in 2000. The average annual amount of funding available per CRP during this period increased by 14%, from US $47,500 in 1999 to US $ 54,000 in 2000. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear

  5. The Research Contract Programme annual report and statistics for 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-06-15

    53 Coordinated Research Projects (CRPs) were completed in 2000. 38 of these CRPs concerned topics in Nuclear Sciences and Applications and 15 were related to nuclear energy and safety. These CRPs were funded for $9,275,648; the average annual cost per CRP was $38,892. A list of these CRPs is included. Evaluations of these CRPs will be completed by the end of 2001 and included in the next annual report. The Agency's unique position as a technical international organization has enabled it to act as an international platform to lead groups of nuclear scientists by co-ordinating research and developmental activities addressing important problems in Member States. CRPs have been used to transfer existing technologies to developing countries, as well as for the development of new technologies in those countries. Since CRPs are tailored to finding solutions to specific problems, as compared to general techniques, their potential value in terms of the effect on Member States' level of development is substantial. In an effort to further enhance the effectiveness of CRPs developed and coordinated by the Agency, various initiatives have been suggested and the Research Contract Programme has been the subject of several advisory fora. The PPAS of Major Programme 2, the Senior Evaluation Group (SEG), and an internal audit of the programme have recently made recommendations to this end. Based on these reviews, the Agency has begun to fund fewer, but better focused and more substantially funded CRPs. Whereas in 1999, the Agency was carrying out 159 CRPs, 132 CRPs were carried out in 2000. The average annual amount of funding available per CRP during this period increased by 14%, from US $47,500 in 1999 to US $ 54,000 in 2000. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear

  6. Road Safety Data, Collection, Transfer and Analysis DaCoTa. Workpackage 3, Deliverable No. D 3.5: Annual Statistical Report 2011 based on data from CARE / EC from 2000 to 2009.

    NARCIS (Netherlands)

    Brandstaetter, C. Yannis, G. Evgenikos, P. Argyropoulou, E. Papantoniou, P. Broughton, J. Knowles, J. Reurings, M. Vis, M. Pace, J.-P. López de Cozar, E. Martinez-Pérez, C. Sanmartín, J. & Haddak, M.

    2013-01-01

    Road traffic accidents in the Member States of the European Union annually claim about 34.000 lives and leave more than 1.1 million people injured, representing estimated costs of 140 billion Euros. Since 1984, a large number of measures to reduce road accidents have been taken at a regional level.

  7. 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

  8. 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

  9. 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

  10. 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

  11. THE FLUORBOARD A STATISTICALLY BASED DASHBOARD METHOD FOR IMPROVING SAFETY

    International Nuclear Information System (INIS)

    PREVETTE, S.S.

    2005-01-01

    The FluorBoard is a statistically based dashboard method for improving safety. Fluor Hanford has achieved significant safety improvements--including more than a 80% reduction in OSHA cases per 200,000 hours, during its work at the US Department of Energy's Hanford Site in Washington state. The massive project on the former nuclear materials production site is considered one of the largest environmental cleanup projects in the world. Fluor Hanford's safety improvements were achieved by a committed partnering of workers, managers, and statistical methodology. Safety achievements at the site have been due to a systematic approach to safety. This includes excellent cooperation between the field workers, the safety professionals, and management through OSHA Voluntary Protection Program principles. Fluor corporate values are centered around safety, and safety excellence is important for every manager in every project. In addition, Fluor Hanford has utilized a rigorous approach to using its safety statistics, based upon Dr. Shewhart's control charts, and Dr. Deming's management and quality methods

  12. Statistical analysis applied to safety culture self-assessment

    International Nuclear Information System (INIS)

    Macedo Soares, P.P.

    2002-01-01

    Interviews and opinion surveys are instruments used to assess the safety culture in an organization as part of the Safety Culture Enhancement Programme. Specific statistical tools are used to analyse the survey results. This paper presents an example of an opinion survey with the corresponding application of the statistical analysis and the conclusions obtained. Survey validation, Frequency statistics, Kolmogorov-Smirnov non-parametric test, Student (T-test) and ANOVA means comparison tests and LSD post-hoc multiple comparison test, are discussed. (author)

  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. Statistical Hot Channel Factors and Safety Limit CHFR/OFIR

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byeonghee; Park, Suki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The fuel integrity of research reactors are usually judged by comparing the critical heat flux ratio (CHFR) and the maximum fuel temperature (MFT) with the safety limits. Onset of flow instability ratio (OFIR) can also be used for the examination with CHFR. Hot channel factors (HCFs) are incorporated when calculating the CHFR/OFIR and MFT, to consider the uncertainties of fuel properties and thermo-hydraulic variables affecting them. The HCFs and safety limit CHFR is sometimes estimated to include too much conservatism, deteriorating the design flexibilities and operating margins. In this paper, a statistical estimation of HCFs and the safety limit CHFR/OFIR is presented by a random sampling of uncertainty parameters. A 15MW pool type research reactor is selected as the sample reactor for the estimation. The HCFs and the safety limit CHFR/OFIR of a 15MW pool type research reactor are evaluated statistically. The parameters affecting the HCF and the safety limit CHFR/OFIR are listed and their uncertainties are estimated. The relevant parameter uncertainties are sampled randomly and the HCFs and the safety limits are evaluated from them. The HCFs and the safety limit CHFR/OFIR with 95% probability are smaller than those estimated deterministically because the statistical evaluation convolute the correlation uncertainties and the other uncertainties in probabilistic way, whereas the deterministic evaluation simply multiply them.

  16. 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

  17. 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...

  18. 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

  19. 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

  20. 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

  1. 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

  2. CBP Intellectual Property Rights (IPR) Annual Seizure Statistics

    Data.gov (United States)

    Department of Homeland Security — Products that infringe on U.S. trademarks, copyrights, and patents threaten the health and safety of American consumers,our economy, and our national security. U.S....

  3. Exploring the temporal stability of global road safety statistics.

    Science.gov (United States)

    Dimitriou, Loukas; Nikolaou, Paraskevas; Antoniou, Constantinos

    2018-02-08

    Given the importance of rigorous quantitative reasoning in supporting national, regional or global road safety policies, data quality, reliability, and stability are of the upmost importance. This study focuses on macroscopic properties of road safety statistics and the temporal stability of these statistics at a global level. A thorough investigation of two years of measurements was conducted to identify any unexpected gaps that could highlight the existence of inconsistent measurements. The database used in this research includes 121 member countries of the United Nation (UN-121) with a population of at least one million (smaller country data shows higher instability) and includes road safety and socioeconomic variables collected from a number of international databases (e.g. WHO and World Bank) for the years 2010 and 2013. For the fulfillment of the earlier stated goal, a number of data visualization and exploratory analyses (Hierarchical Clustering and Principal Component Analysis) were conducted. Furthermore, in order to provide a richer analysis of the data, we developed and compared the specification of a number of Structural Equation Models for the years 2010 and 2013. Different scenarios have been developed, with different endogenous variables (indicators of mortality rate and fatality risk) and structural forms. The findings of the current research indicate inconsistency phenomena in global statistics of different instances/years. Finally, the results of this research provide evidence on the importance of careful and systematic data collection for developing advanced statistical and econometric techniques and furthermore for developing road safety policies. Copyright © 2017 Elsevier Ltd. All rights reserved.

  4. 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...

  5. 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

  6. 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

  7. Alberta oil and gas industry annual statistics for 1998

    International Nuclear Information System (INIS)

    1999-07-01

    Annual prices and deliveries are provided by resource commodity, along with a summary of province-wide drilling activity for 1998 covering annual well count and depths drilled. By commodity information is provided: 1) supply and disposition of crude oil and its equivalent for 1998 and historically, 2) from a 1998 and historical perspective the supply and disposition of gas 3) for 1998 and historically the supply and disposition of ethane, 4) for 1998 and historically the supply and disposition of propane, 5) for 1998 and historically the supply and disposition of butanes, 6) for 1998 and historically the supply and disposition of NGL mixes, 7) for 1998 and historically the supply and disposition of sulfur. 25 figs

  8. 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...

  9. 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

  10. 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

  11. Statistical margin to DNB safety analysis approach for LOFT

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1982-01-01

    A method was developed and used for LOFT thermal safety analysis to estimate the statistical margin to DNB for the hot rod, and to base safety analysis on desired DNB probability limits. This method is an advanced approach using response surface analysis methods, a very efficient experimental design, and a 2nd-order response surface equation with a 2nd-order error propagation analysis to define the MDNBR probability density function. Calculations for limiting transients were used in the response surface analysis thereby including transient interactions and trip uncertainties in the MDNBR probability density

  12. 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...

  13. 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

  14. Statistical annual report 2008 - Furnas Electric Power Plants Inc. - Calendar year 2007

    International Nuclear Information System (INIS)

    2008-01-01

    This 30th edition of the statistical annual report of Furnas reports the performance of the company in 2007 and recent years allowing a general view on: Furnas system; production and supply; financial and economic data, personnel and indicators

  15. Summary of Key Operating Statistics: Data Collected from the 2009 Annual Institutional Report

    Science.gov (United States)

    Accrediting Council for Independent Colleges and Schools, 2010

    2010-01-01

    The Accrediting Council for Independent Colleges and Schools (ACICS) provides the Summary of Key Operating Statistics (KOS) as an annual review of the performance and key measurements of the more than 800 private post-secondary institutions we accredit. This edition of the KOS contains information based on the 2009 Annual Institutional Reports…

  16. Northern Ireland annual abstract of statistics: no. 9

    International Nuclear Information System (INIS)

    1990-01-01

    These 1990 statistics from the Policy Planning and Research Unit at Stormont, which form part of a larger non-nuclear collection, detail radioactive contamination of fish and seaweeds in the Irish Sea, in terms of the concentrations of K 40 , Cs 134 and Cs 137 in Becquerels per kilogram. Gamma doses in intertidal sediments of sand and mud are also recorded. (UK)

  17. Annual statistic report - Furnas Centrais Eletricas S.A. - 1995

    International Nuclear Information System (INIS)

    1995-01-01

    In this report, extensive statistical data concerning the 1994 activities of the electric utility Furnas Centrais Eletricas S.A. are presented. They include the consumer's market, the generation and supply of electricity and economic and personal information. 106 figs., 71 tabs

  18. Additional methodology development for statistical evaluation of reactor safety analyses

    International Nuclear Information System (INIS)

    Marshall, J.A.; Shore, R.W.; Chay, S.C.; Mazumdar, M.

    1977-03-01

    The project described is motivated by the desire for methods to quantify uncertainties and to identify conservatisms in nuclear power plant safety analysis. The report examines statistical methods useful for assessing the probability distribution of output response from complex nuclear computer codes, considers sensitivity analysis and several other topics, and also sets the path for using the developed methods for realistic assessment of the design basis accident

  19. The Association of Academic Health Sciences Libraries Annual Statistics: a thematic history.

    Science.gov (United States)

    Shedlock, James; Byrd, Gary D

    2003-04-01

    The Annual Statistics of Medical School Libraries in the United States and Canada (Annual Statistics) is the most recognizable achievement of the Association of Academic Health Sciences Libraries in its history to date. This article gives a thematic history of the Annual Statistics, emphasizing the leadership role of editors and Editorial Boards, the need for cooperation and membership support to produce comparable data useful for everyday management of academic medical center libraries and the use of technology as a tool for data gathering and publication. The Annual Statistics' origin is recalled, and survey features and content are related to the overall themes. The success of the Annual Statistics is evident in the leadership skills of the first editor, Richard Lyders, executive director of the Houston Academy of Medicine-Texas Medical Center Library. The history shows the development of a survey instrument that strives to produce reliable and valid data for a diverse group of libraries while reflecting the many complex changes in the library environment. The future of the Annual Statistics is assured by the anticipated changes facing academic health sciences libraries, namely the need to reflect the transition from a physical environment to an electronic operation.

  20. Annual bulletin of gas statistics for Europe, 1974. Vol. XX

    Energy Technology Data Exchange (ETDEWEB)

    1975-01-01

    The report provides basic data on developments and trends in the field of gaseous fuels in European countries and the USA. The data refer to production, stocks, inland availabilities, deliveries, trade, calorific values, fuels used for the production of gasworks gas, number of household consumers, and length of mines. The statistics appearing in this bulletin are compiled by the secretariat of the United Nations Economic Commission for Europe from replies to questionnaires supplied by various countries, or from official national sources. The statistics are presented in the form of time series. Figures are given for 1970 to 1974. In the tables relating to trade and length of mains, figures are given for 1973 and 1974.

  1. 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...

  2. Coordinated research activities: Annual report and statistics for 2006

    International Nuclear Information System (INIS)

    2007-07-01

    In 2006, a total of Euro 5 622 290 from the regular budget and Euro 130 715 of extra budgetary contributions were awarded in support of Coordinated Research Projects (CRPs). The CRPs were in Major Programme 1 - Nuclear Power, Fuel Cycle and Nuclear Science, in Major Programme 2 - Nuclear Techniques for Development and Environmental Protection, and in Major Programme 3 - Nuclear Safety and Security. Compared with 2005, the amount awarded represented 20% lower financial support because of completion of 39 CRPs, but with only 19 new start-ups CRPs. Over 70% of the funds awarded for contracts were made to institutions in developing countries primarily in the areas of nuclear power, nuclear science, waste management, food and agriculture, human health, water resources and isotope hydrology, and nuclear safety and security. In numerical terms, at the end of 2006 there were 1385 contracts and agreements awarded to institutes in 108 Member States. The total number of contracts includes 772 research contracts and 107 technical contracts. In addition, 506 research agreements were awarded. Notwithstanding the Secretariat's efforts to increase the numbers of female Chief Scientific Investigators participating in CRPs, the percentage remained at 20%. Efforts continue to increase this figure. The completed CRPs resulted in one PhD, 5 master's degrees and 5 other theses and dissertations, and in the publishing of about 769 articles and reports, scientific papers, proceedings of scientific conferences and contribution to international conferences as well as 11 IAEA TECDOCs, a new scientific database and one website. Detailed reports on the outputs, effectiveness, impact, recommended future action, and resulting publications are listed in Appendix E of this report

  3. Implications of Monte Carlo Statistical Errors in Criticality Safety Assessments

    International Nuclear Information System (INIS)

    Pevey, Ronald E.

    2005-01-01

    Most criticality safety calculations are performed using Monte Carlo techniques because of Monte Carlo's ability to handle complex three-dimensional geometries. For Monte Carlo calculations, the more histories sampled, the lower the standard deviation of the resulting estimates. The common intuition is, therefore, that the more histories, the better; as a result, analysts tend to run Monte Carlo analyses as long as possible (or at least to a minimum acceptable uncertainty). For Monte Carlo criticality safety analyses, however, the optimization situation is complicated by the fact that procedures usually require that an extra margin of safety be added because of the statistical uncertainty of the Monte Carlo calculations. This additional safety margin affects the impact of the choice of the calculational standard deviation, both on production and on safety. This paper shows that, under the assumptions of normally distributed benchmarking calculational errors and exact compliance with the upper subcritical limit (USL), the standard deviation that optimizes production is zero, but there is a non-zero value of the calculational standard deviation that minimizes the risk of inadvertently labeling a supercritical configuration as subcritical. Furthermore, this value is shown to be a simple function of the typical benchmarking step outcomes--the bias, the standard deviation of the bias, the upper subcritical limit, and the number of standard deviations added to calculated k-effectives before comparison to the USL

  4. 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

  5. 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

  6. 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)

  7. Coordinated research activities: Annual report and statistics for 2004

    International Nuclear Information System (INIS)

    2005-05-01

    , including current information on CRPs and programme areas supported, information on policies and procedures and the administration of the activities is contained in the Agency's Coordinated Research Activities website at: http://www-crp.iaea.org. The Coordinated Research Activities reported in this document are conducted in support of the following Agency programmes: Nuclear Power; Nuclear Fuel Cycle and Materials Technologies; Capacity Building and Nuclear Knowledge Maintenance for Sustainable Energy Development; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation and Transport Safety; Management of Radioactive Waste; Nuclear Security. Results of research are available to all Member States and are disseminated through, national, international and Agency scientific and technical publications. The Coordinated Research Activities are complementary to its Technical Cooperation Projects, with the knowledge gained via coordinated research used to enhance the quality of Technical Cooperation Projects. In terms of benefits to Member States through their participating research institutions, number of awards and degree of funding, coordinated research activities constitute a significant component of the Agency's overall programme. 942 contracts and agreements were awarded from the 1244 contract and agreement proposals received by the Agency during 2004. In 2004, $6 765 324 were awarded from the regular budget to institutes under contractual arrangements and to fund Research Coordination Meetings (RCMs). Additionally, $230 859 of extra-budgetary contributions were used to fund additional contracts and RCMs. Thus, total awards amounted to $6 996 183. The average award per contract was $6 065

  8. Coordinated research activities: Annual report and statistics for 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-05-15

    , including current information on CRPs and programme areas supported, information on policies and procedures and the administration of the activities is contained in the Agency's Coordinated Research Activities website at: http://www-crp.iaea.org. The Coordinated Research Activities reported in this document are conducted in support of the following Agency programmes: Nuclear Power; Nuclear Fuel Cycle and Materials Technologies; Capacity Building and Nuclear Knowledge Maintenance for Sustainable Energy Development; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation and Transport Safety; Management of Radioactive Waste; Nuclear Security. Results of research are available to all Member States and are disseminated through, national, international and Agency scientific and technical publications. The Coordinated Research Activities are complementary to its Technical Cooperation Projects, with the knowledge gained via coordinated research used to enhance the quality of Technical Cooperation Projects. In terms of benefits to Member States through their participating research institutions, number of awards and degree of funding, coordinated research activities constitute a significant component of the Agency's overall programme. 942 contracts and agreements were awarded from the 1244 contract and agreement proposals received by the Agency during 2004. In 2004, $6 765 324 were awarded from the regular budget to institutes under contractual arrangements and to fund Research Coordination Meetings (RCMs). Additionally, $230 859 of extra-budgetary contributions were used to fund additional contracts and RCMs. Thus, total awards amounted to $6 996 183. The average award per contract was $6 065.

  9. Coordinated research activities: Annual report and statistics for 2005

    International Nuclear Information System (INIS)

    2006-06-01

    in the website at: http://cra.iaea.org/. The Coordinated Research Activities reported in this document are conducted in support of the following Agency programmes: Nuclear Power; Nuclear Fuel Cycle and Materials Technologies; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation and Transport Safety; Management of Radioactive Waste; Nuclear Security. Results of research are available to all Member States and are disseminated through, national, international and Agency scientific and technical publications. The Coordinated Research Activities are complementary to its Technical Cooperation Projects, with the knowledge gained via coordinated research used to enhance the quality of Technical Cooperation Projects. Some research results are directly relevant to Technical Cooperation Projects and lead to successful implementation of these projects, while some Technical Projects lead to participation in Coordinated Research Activities. In addition, CRPs and TC Projects may also be carried out simultaneously. In terms of benefits to Member States through their participating research institutions, number of awards and degree of funding, coordinated research activities constitute a significant component of the Agency's overall programme. 765 contracts and 142 agreements were awarded from the 1170 proposals (992 contract proposals and 178 agreement proposals) received by the Agency during 2005. Annex I lists, by country, the number of proposals received and awards made. In 2005, $7 223 923 from the regular budget, ($166 566 thereof from 2004 unobligated funds), and $169 590 of extra-budgetary contributions totaling $7 393 513 were awarded to institutes under contractual arrangements and to fund Research Coordination Meetings (RCMs). The average award per contract was $6 440, about 6% more than the 2004 average award level

  10. Coordinated research activities: Annual report and statistics for 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-06-15

    in the website at: http://cra.iaea.org/. The Coordinated Research Activities reported in this document are conducted in support of the following Agency programmes: Nuclear Power; Nuclear Fuel Cycle and Materials Technologies; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation and Transport Safety; Management of Radioactive Waste; Nuclear Security. Results of research are available to all Member States and are disseminated through, national, international and Agency scientific and technical publications. The Coordinated Research Activities are complementary to its Technical Cooperation Projects, with the knowledge gained via coordinated research used to enhance the quality of Technical Cooperation Projects. Some research results are directly relevant to Technical Cooperation Projects and lead to successful implementation of these projects, while some Technical Projects lead to participation in Coordinated Research Activities. In addition, CRPs and TC Projects may also be carried out simultaneously. In terms of benefits to Member States through their participating research institutions, number of awards and degree of funding, coordinated research activities constitute a significant component of the Agency's overall programme. 765 contracts and 142 agreements were awarded from the 1170 proposals (992 contract proposals and 178 agreement proposals) received by the Agency during 2005. Annex I lists, by country, the number of proposals received and awards made. In 2005, $7 223 923 from the regular budget, ($166 566 thereof from 2004 unobligated funds), and $169 590 of extra-budgetary contributions totaling $7 393 513 were awarded to institutes under contractual arrangements and to fund Research Coordination Meetings (RCMs). The average award per contract was $6 440, about 6% more than the 2004 average award level.

  11. Coordinated research activities: Annual report and statistics for 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-15

    In 2007, a total of Euro 6 606 194 were obligated for the Agency's Coordinated Research Activities (Euro 6 515 957 from the regular budget and Euro 90 237 from extrabudgetary resources). Most of the Coordinated Research Activities are carried out via Coordinated Research Projects (CRPs) which bring together research institutes in both developing and developed Member States to collaborate on research topics of common interest. At the end of 2007, work was being carried out on 115 CRPs, 37 in Major Programme 1 - Nuclear Power, Fuel Cycle and Nuclear Science, 71 in Major Programme 2 - Nuclear Techniques for Development and Environmental Protection, and 7 in Major Programme 3 - Nuclear Safety and Security. The total amount obligated for these activities in 2007 was 15% more than in 2006, largely due to the implementation of 28 new CRPs. At the end of 2007 work was being carried out under 976 contracts and 562 agreements with institutes in 110 Member States. 72% of the funds obligated for contracts in 2007 were in respect of institutions in developing countries, primarily in the areas of food and agriculture and human health. During 2007, 21% of the Chief Scientific Investigators participating in Agency CRPs were female researchers. Efforts will continue to increase the participation of women and younger researcher in the Coordinated Research Activities. The forty two completed CRPs evaluated in Appendix E resulted in 9 PhDs, one masters degree and in the publishing of about 800 articles and reports, scientific papers, proceedings of scientific conferences and contribution to international conferences, as well as 13 IAEA TECDOCs, and various scientific databases and websites. Detailed evaluation reports on the outputs, effectiveness, impact, recommended future action, and resulting publications of these completed CRPs are included in in Appendix E of this report. (author)

  12. Coordinated research activities: Annual report and statistics for 2007

    International Nuclear Information System (INIS)

    2008-07-01

    In 2007, a total of Euro 6 606 194 were obligated for the Agency's Coordinated Research Activities (Euro 6 515 957 from the regular budget and Euro 90 237 from extrabudgetary resources). Most of the Coordinated Research Activities are carried out via Coordinated Research Projects (CRPs) which bring together research institutes in both developing and developed Member States to collaborate on research topics of common interest. At the end of 2007, work was being carried out on 115 CRPs, 37 in Major Programme 1 - Nuclear Power, Fuel Cycle and Nuclear Science, 71 in Major Programme 2 - Nuclear Techniques for Development and Environmental Protection, and 7 in Major Programme 3 - Nuclear Safety and Security. The total amount obligated for these activities in 2007 was 15% more than in 2006, largely due to the implementation of 28 new CRPs. At the end of 2007 work was being carried out under 976 contracts and 562 agreements with institutes in 110 Member States. 72% of the funds obligated for contracts in 2007 were in respect of institutions in developing countries, primarily in the areas of food and agriculture and human health. During 2007, 21% of the Chief Scientific Investigators participating in Agency CRPs were female researchers. Efforts will continue to increase the participation of women and younger researcher in the Coordinated Research Activities. The forty two completed CRPs evaluated in Appendix E resulted in 9 PhDs, one masters degree and in the publishing of about 800 articles and reports, scientific papers, proceedings of scientific conferences and contribution to international conferences, as well as 13 IAEA TECDOCs, and various scientific databases and websites. Detailed evaluation reports on the outputs, effectiveness, impact, recommended future action, and resulting publications of these completed CRPs are included in in Appendix E of this report. (author)

  13. 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...

  14. Oberbergamt fuer das Saarland und das Land Rheinland-Pfalz, Bergamt Saarbruecken / Bergamt Rheinland-Pfalz. Annual report 1998. Economic and technical aspects, industrial safety and environmental protection, statistics, activities of the mining authorities; Oberbergamt fuer das Saarland und das Land Rheinland-Pfalz, Bergamt Saarbruecken / Bergamt Rheinland-Pfalz. Jahresbericht 1998. Bergwirtschaft, Bergtechnik, Arbeitsschutz, Umweltschutz, Statistiken, Taetigkeiten der Bergbehoerde

    Energy Technology Data Exchange (ETDEWEB)

    Boettcher, R.; Hugo, K.H.; Kuhn, M.; Strauch, T. [comps.

    1999-07-01

    After outlining developmental trends in the various mining sectors as well as the structure and tasks of the State Mines Inspectorate, the annual report describes the activities in the fields of health and industrial safety, mining engineering and safety, and the environmental effects of mining activities, as well as special accidents and incidents. (HS) [German] Nach einem Ueberblick ueber die bergwirtschaftliche Entwicklung in den einzelnen Bergbauzweigen sowie ueber den Aufbau und die Zustaendigkeit der Bergbehoerde werden die Aktivitaeten in den Bereichen Arbeits- und Gesundheitsschutz, Bergtechnik und Sicherheit, Bergbau und Umwelt sowie bemerkenswerte Unfaelle und Vorkommnisse beschrieben. (HS)

  15. Reliability assessment for safety critical systems by statistical random testing

    International Nuclear Information System (INIS)

    Mills, S.E.

    1995-11-01

    In this report we present an overview of reliability assessment for software and focus on some basic aspects of assessing reliability for safety critical systems by statistical random testing. We also discuss possible deviations from some essential assumptions on which the general methodology is based. These deviations appear quite likely in practical applications. We present and discuss possible remedies and adjustments and then undertake applying this methodology to a portion of the SDS1 software. We also indicate shortcomings of the methodology and possible avenues to address to follow to address these problems. (author). 128 refs., 11 tabs., 31 figs

  16. Reliability assessment for safety critical systems by statistical random testing

    Energy Technology Data Exchange (ETDEWEB)

    Mills, S E [Carleton Univ., Ottawa, ON (Canada). Statistical Consulting Centre

    1995-11-01

    In this report we present an overview of reliability assessment for software and focus on some basic aspects of assessing reliability for safety critical systems by statistical random testing. We also discuss possible deviations from some essential assumptions on which the general methodology is based. These deviations appear quite likely in practical applications. We present and discuss possible remedies and adjustments and then undertake applying this methodology to a portion of the SDS1 software. We also indicate shortcomings of the methodology and possible avenues to address to follow to address these problems. (author). 128 refs., 11 tabs., 31 figs.

  17. 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

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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.

  6. On statistical inference in time series analysis of the evolution of road safety.

    Science.gov (United States)

    Commandeur, Jacques J F; Bijleveld, Frits D; Bergel-Hayat, Ruth; Antoniou, Constantinos; Yannis, George; Papadimitriou, Eleonora

    2013-11-01

    Data collected for building a road safety observatory usually include observations made sequentially through time. Examples of such data, called time series data, include annual (or monthly) number of road traffic accidents, traffic fatalities or vehicle kilometers driven in a country, as well as the corresponding values of safety performance indicators (e.g., data on speeding, seat belt use, alcohol use, etc.). Some commonly used statistical techniques imply assumptions that are often violated by the special properties of time series data, namely serial dependency among disturbances associated with the observations. The first objective of this paper is to demonstrate the impact of such violations to the applicability of standard methods of statistical inference, which leads to an under or overestimation of the standard error and consequently may produce erroneous inferences. Moreover, having established the adverse consequences of ignoring serial dependency issues, the paper aims to describe rigorous statistical techniques used to overcome them. In particular, appropriate time series analysis techniques of varying complexity are employed to describe the development over time, relating the accident-occurrences to explanatory factors such as exposure measures or safety performance indicators, and forecasting the development into the near future. Traditional regression models (whether they are linear, generalized linear or nonlinear) are shown not to naturally capture the inherent dependencies in time series data. Dedicated time series analysis techniques, such as the ARMA-type and DRAG approaches are discussed next, followed by structural time series models, which are a subclass of state space methods. The paper concludes with general recommendations and practice guidelines for the use of time series models in road safety research. Copyright © 2012 Elsevier Ltd. All rights reserved.

  7. Statistical annual report 2003 of Furnas - Electrical Power plants and Co., RJ, Brazil. Calendar year 2003

    International Nuclear Information System (INIS)

    2003-01-01

    This document presents the statistical annual report of Furnas Power Plants and Co, reporting the results obtained during the calendar year of 2003 and the evolution in the last five years, allowing a general and comparative views of the company performance focusing the power generation and transmission, economic and financial results

  8. 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.

  9. 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...

  10. 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...

  11. 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

  12. Methodology development for statistical evaluation of reactor safety analyses

    International Nuclear Information System (INIS)

    Mazumdar, M.; Marshall, J.A.; Chay, S.C.; Gay, R.

    1976-07-01

    In February 1975, Westinghouse Electric Corporation, under contract to Electric Power Research Institute, started a one-year program to develop methodology for statistical evaluation of nuclear-safety-related engineering analyses. The objectives of the program were to develop an understanding of the relative efficiencies of various computational methods which can be used to compute probability distributions of output variables due to input parameter uncertainties in analyses of design basis events for nuclear reactors and to develop methods for obtaining reasonably accurate estimates of these probability distributions at an economically feasible level. A series of tasks was set up to accomplish these objectives. Two of the tasks were to investigate the relative efficiencies and accuracies of various Monte Carlo and analytical techniques for obtaining such estimates for a simple thermal-hydraulic problem whose output variable of interest is given in a closed-form relationship of the input variables and to repeat the above study on a thermal-hydraulic problem in which the relationship between the predicted variable and the inputs is described by a short-running computer program. The purpose of the report presented is to document the results of the investigations completed under these tasks, giving the rationale for choices of techniques and problems, and to present interim conclusions

  13. 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

  14. 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

  15. Brazilian energy statistics - 1989. Annual bulletin of the Brazilian National Committee of the World Energy Conference

    International Nuclear Information System (INIS)

    1989-01-01

    This bulletin deals with the primary sources that carry most weight in the Brazilian energy balance: hydraulic energy, petroleum, natural gas and coal. It contains data on ethyl alcohol derived from sugar cane and some aspects about nuclear energy in Brazil. Graphs, annual statistics and historical data of electric power, petroleum and petroleum products, natural gas, coal and alcohol are also included. 17 figs., 12 tabs

  16. Brazilian energy statistics - 1988. Annual bulletin of the Brazilian National Committee of the World Energy Conference

    International Nuclear Information System (INIS)

    1988-01-01

    This bulletin deals with the primary sources that carry most weight in the Brazilian energy balance: hydraulic energy, petroleum, natural gas and coal. It contains data on ethyl alcohol derived from sugar cane and some information about the Brazilian Action Plan for the petroleum sector, nuclear energy, ecology and Chernobyl. Graphs, annual statistics and long range data of electric power, petroleum and derivates, natural gas, coal and alcohol are also included. 19 figs., 15 tabs

  17. Annual Statistical Report of the Public School of Arkansas and Education Service Cooperatives

    Science.gov (United States)

    Arkansas Department of Education, 2016

    2016-01-01

    In compliance with the provisions of A.C.A.§§6-20-2201 et seq., the Annual Statistical Report of the Public Schools of Arkansas, Public Charter Schools, and Education Service Cooperatives, 2014-2015 Actual and 2015-2016 Budgeted, (ASR) is presented here. The Rankings of Selected Items of the Public Schools of Arkansas, 2014-2015 Actual, (Rankings)…

  18. 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...

  19. 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...

  20. 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)

  1. 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).

  2. 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

  3. 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

  4. 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

  5. A Statistical Methodology for Determination of Safety Systems Actuation Setpoints Based on Extreme Value Statistics

    Directory of Open Access Journals (Sweden)

    D. R. Novog

    2008-01-01

    Full Text Available This paper provides a novel and robust methodology for determination of nuclear reactor trip setpoints which accounts for uncertainties in input parameters and models, as well as accounting for the variations in operating states that periodically occur. Further it demonstrates that in performing best estimate and uncertainty calculations, it is critical to consider the impact of all fuel channels and instrumentation in the integration of these uncertainties in setpoint determination. This methodology is based on the concept of a true trip setpoint, which is the reactor setpoint that would be required in an ideal situation where all key inputs and plant responses were known, such that during the accident sequence a reactor shutdown will occur which just prevents the acceptance criteria from being exceeded. Since this true value cannot be established, the uncertainties in plant simulations and plant measurements as well as operational variations which lead to time changes in the true value of initial conditions must be considered. This paper presents the general concept used to determine the actuation setpoints considering the uncertainties and changes in initial conditions, and allowing for safety systems instrumentation redundancy. The results demonstrate unique statistical behavior with respect to both fuel and instrumentation uncertainties which has not previously been investigated.

  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. Statistics

    International Nuclear Information System (INIS)

    2001-01-01

    For the year 2000, part of the figures shown in the tables of the Energy Review are preliminary or estimated. The annual statistics of the Energy Review appear in more detail from the publication Energiatilastot - Energy Statistics issued annually, which also includes historical time series over a longer period (see e.g. Energiatilastot 1999, Statistics Finland, Helsinki 2000, ISSN 0785-3165). The inside of the Review's back cover shows the energy units and the conversion coefficients used for them. Explanatory notes to the statistical tables can be found after tables and figures. The figures presents: Changes in the volume of GNP and energy consumption, Changes in the volume of GNP and electricity, Coal consumption, Natural gas consumption, Peat consumption, Domestic oil deliveries, Import prices of oil, Consumer prices of principal oil products, Fuel prices for heat production, Fuel prices for electricity production, Carbon dioxide emissions from the use of fossil fuels, Total energy consumption by source and CO 2 -emissions, Electricity supply, Energy imports by country of origin in 2000, Energy exports by recipient country in 2000, Consumer prices of liquid fuels, Consumer prices of hard coal, natural gas and indigenous fuels, Average electricity price by type of consumer, Price of district heating by type of consumer, Excise taxes, value added taxes and fiscal charges and fees included in consumer prices of some energy sources and Energy taxes and precautionary stock fees on oil products

  14. Statistics

    International Nuclear Information System (INIS)

    2000-01-01

    For the year 1999 and 2000, part of the figures shown in the tables of the Energy Review are preliminary or estimated. The annual statistics of the Energy Review appear in more detail from the publication Energiatilastot - Energy Statistics issued annually, which also includes historical time series over a longer period (see e.g., Energiatilastot 1998, Statistics Finland, Helsinki 1999, ISSN 0785-3165). The inside of the Review's back cover shows the energy units and the conversion coefficients used for them. Explanatory notes to the statistical tables can be found after tables and figures. The figures presents: Changes in the volume of GNP and energy consumption, Changes in the volume of GNP and electricity, Coal consumption, Natural gas consumption, Peat consumption, Domestic oil deliveries, Import prices of oil, Consumer prices of principal oil products, Fuel prices for heat production, Fuel prices for electricity production, Carbon dioxide emissions, Total energy consumption by source and CO 2 -emissions, Electricity supply, Energy imports by country of origin in January-March 2000, Energy exports by recipient country in January-March 2000, Consumer prices of liquid fuels, Consumer prices of hard coal, natural gas and indigenous fuels, Average electricity price by type of consumer, Price of district heating by type of consumer, Excise taxes, value added taxes and fiscal charges and fees included in consumer prices of some energy sources and Energy taxes and precautionary stock fees on oil products

  15. Statistics

    International Nuclear Information System (INIS)

    1999-01-01

    For the year 1998 and the year 1999, part of the figures shown in the tables of the Energy Review are preliminary or estimated. The annual statistics of the Energy Review appear in more detail from the publication Energiatilastot - Energy Statistics issued annually, which also includes historical time series over a longer period (see e.g. Energiatilastot 1998, Statistics Finland, Helsinki 1999, ISSN 0785-3165). The inside of the Review's back cover shows the energy units and the conversion coefficients used for them. Explanatory notes to the statistical tables can be found after tables and figures. The figures presents: Changes in the volume of GNP and energy consumption, Changes in the volume of GNP and electricity, Coal consumption, Natural gas consumption, Peat consumption, Domestic oil deliveries, Import prices of oil, Consumer prices of principal oil products, Fuel prices for heat production, Fuel prices for electricity production, Carbon dioxide emissions, Total energy consumption by source and CO 2 -emissions, Electricity supply, Energy imports by country of origin in January-June 1999, Energy exports by recipient country in January-June 1999, Consumer prices of liquid fuels, Consumer prices of hard coal, natural gas and indigenous fuels, Average electricity price by type of consumer, Price of district heating by type of consumer, Excise taxes, value added taxes and fiscal charges and fees included in consumer prices of some energy sources and Energy taxes and precautionary stock fees on oil products

  16. 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.

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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...

  2. 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...

  3. 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...

  4. 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)

  5. 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.)

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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.)

  17. 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

  18. 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

  19. 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)

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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...

  5. 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.)

  6. 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.)

  7. Safety bey statistics? A critical view on statistical methods applied in health physics

    International Nuclear Information System (INIS)

    Kraut, W.

    2016-01-01

    The only proper way to describe uncertainties in health physics is by statistical means. But statistics never can replace Your personal evaluation of effect, nor can statistics transmute randomness into certainty like an ''uncertainty laundry''. The paper discusses these problems in routine practical work.

  8. 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

  9. 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.)

  10. 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)

  11. 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

  12. 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.

  13. 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

  14. 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

  15. 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)

  16. 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....

  17. 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.

  18. 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)

  19. 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)

  20. 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

  1. 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)

  2. 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)

  3. Bayesian Statistics and Uncertainty Quantification for Safety Boundary Analysis in Complex Systems

    Science.gov (United States)

    He, Yuning; Davies, Misty Dawn

    2014-01-01

    The analysis of a safety-critical system often requires detailed knowledge of safe regions and their highdimensional non-linear boundaries. We present a statistical approach to iteratively detect and characterize the boundaries, which are provided as parameterized shape candidates. Using methods from uncertainty quantification and active learning, we incrementally construct a statistical model from only few simulation runs and obtain statistically sound estimates of the shape parameters for safety boundaries.

  4. 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.)

  5. 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.)

  6. 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.).

  7. 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.)

  8. 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)

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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.)

  17. 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)

  18. 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)

  19. 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

  20. 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.)

  1. 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

  2. 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.)

  3. 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.)

  4. 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

  5. Statistics

    International Nuclear Information System (INIS)

    2005-01-01

    For the years 2004 and 2005 the figures shown in the tables of Energy Review are partly preliminary. The annual statistics published in Energy Review are presented in more detail in a publication called Energy Statistics that comes out yearly. Energy Statistics also includes historical time-series over a longer period of time (see e.g. Energy Statistics, Statistics Finland, Helsinki 2004.) The applied energy units and conversion coefficients are shown in the back cover of the Review. Explanatory notes to the statistical tables can be found after tables and figures. The figures presents: Changes in GDP, energy consumption and electricity consumption, Carbon dioxide emissions from fossile fuels use, Coal consumption, Consumption of natural gas, Peat consumption, Domestic oil deliveries, Import prices of oil, Consumer prices of principal oil products, Fuel prices in heat production, Fuel prices in electricity production, Price of electricity by type of consumer, Average monthly spot prices at the Nord pool power exchange, Total energy consumption by source and CO 2 -emissions, Supplies and total consumption of electricity GWh, Energy imports by country of origin in January-June 2003, Energy exports by recipient country in January-June 2003, Consumer prices of liquid fuels, Consumer prices of hard coal, natural gas and indigenous fuels, Price of natural gas by type of consumer, Price of electricity by type of consumer, Price of district heating by type of consumer, Excise taxes, value added taxes and fiscal charges and fees included in consumer prices of some energy sources and Energy taxes, precautionary stock fees and oil pollution fees

  6. Rationale for statistical characteristics of road safety parameters

    Directory of Open Access Journals (Sweden)

    Dormidontova Tatiana

    2017-01-01

    Full Text Available When making engineering decisions at the stage of designing auto-roads and man-made structures it is necessary to take into account the statistical variability of physical and mechanical characteristics of the used materials as well as the different effects on the structures. Thus the rationale for the statistical characteristics of the parameters that determine the reliability of roads and man-made engineering facilities is of particular importance.There are many factors to be considered while designing roads, such as natural climatic factors, the accidental effects of the operating loads, the strength and deformation characteristics of the materials, the geometric parameters of the structure, etc. which affect the strength characteristics of roads and man-made structures. The rationale for statistical characteristics of the parameters can help an engineer assess the reliability of the decision and the economic risk, as well as avoid making mistakes in the design of roads and man-made structures.However, some statistical characteristics of the parameters that define the reliability of a road and man-made structures play a key role in the design. These are the visibility distance in daytime for the peak curve, variation coefficient of radial acceleration, the reliability of visibility distance and other parameters.

  7. 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

  8. 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

  9. 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

  10. 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...

  11. 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.)

  12. 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

  13. 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)

  14. 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

  15. Current statistical tools, systems and bodies concerned with safety and accident statistics.

    NARCIS (Netherlands)

    Koornstra, M.J.

    1996-01-01

    There are a wide range of differences in the methods used nationally to classify and record road accidents. The current use of road safety information systems and the few systems available for international use are discussed. Recommendations are made for a more efficient, less costly, and improved

  16. 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

  17. Statistics

    International Nuclear Information System (INIS)

    2003-01-01

    For the year 2002, part of the figures shown in the tables of the Energy Review are partly preliminary. The annual statistics of the Energy Review also includes historical time-series over a longer period (see e.g. Energiatilastot 2001, Statistics Finland, Helsinki 2002). The applied energy units and conversion coefficients are shown in the inside back cover of the Review. Explanatory notes to the statistical tables can be found after tables and figures. The figures presents: Changes in GDP, energy consumption and electricity consumption, Carbon dioxide emissions from fossile fuels use, Coal consumption, Consumption of natural gas, Peat consumption, Domestic oil deliveries, Import prices of oil, Consumer prices of principal oil products, Fuel prices in heat production, Fuel prices in electricity production, Price of electricity by type of consumer, Average monthly spot prices at the Nord pool power exchange, Total energy consumption by source and CO 2 -emissions, Supply and total consumption of electricity GWh, Energy imports by country of origin in January-June 2003, Energy exports by recipient country in January-June 2003, Consumer prices of liquid fuels, Consumer prices of hard coal, natural gas and indigenous fuels, Price of natural gas by type of consumer, Price of electricity by type of consumer, Price of district heating by type of consumer, Excise taxes, value added taxes and fiscal charges and fees included in consumer prices of some energy sources and Excise taxes, precautionary stock fees on oil pollution fees on energy products

  18. Statistics

    International Nuclear Information System (INIS)

    2004-01-01

    For the year 2003 and 2004, the figures shown in the tables of the Energy Review are partly preliminary. The annual statistics of the Energy Review also includes historical time-series over a longer period (see e.g. Energiatilastot, Statistics Finland, Helsinki 2003, ISSN 0785-3165). The applied energy units and conversion coefficients are shown in the inside back cover of the Review. Explanatory notes to the statistical tables can be found after tables and figures. The figures presents: Changes in GDP, energy consumption and electricity consumption, Carbon dioxide emissions from fossile fuels use, Coal consumption, Consumption of natural gas, Peat consumption, Domestic oil deliveries, Import prices of oil, Consumer prices of principal oil products, Fuel prices in heat production, Fuel prices in electricity production, Price of electricity by type of consumer, Average monthly spot prices at the Nord pool power exchange, Total energy consumption by source and CO 2 -emissions, Supplies and total consumption of electricity GWh, Energy imports by country of origin in January-March 2004, Energy exports by recipient country in January-March 2004, Consumer prices of liquid fuels, Consumer prices of hard coal, natural gas and indigenous fuels, Price of natural gas by type of consumer, Price of electricity by type of consumer, Price of district heating by type of consumer, Excise taxes, value added taxes and fiscal charges and fees included in consumer prices of some energy sources and Excise taxes, precautionary stock fees on oil pollution fees

  19. Statistics

    International Nuclear Information System (INIS)

    2000-01-01

    For the year 1999 and 2000, part of the figures shown in the tables of the Energy Review are preliminary or estimated. The annual statistics of the Energy also includes historical time series over a longer period (see e.g., Energiatilastot 1999, Statistics Finland, Helsinki 2000, ISSN 0785-3165). The inside of the Review's back cover shows the energy units and the conversion coefficients used for them. Explanatory notes to the statistical tables can be found after tables and figures. The figures presents: Changes in the volume of GNP and energy consumption, Changes in the volume of GNP and electricity, Coal consumption, Natural gas consumption, Peat consumption, Domestic oil deliveries, Import prices of oil, Consumer prices of principal oil products, Fuel prices for heat production, Fuel prices for electricity production, Carbon dioxide emissions, Total energy consumption by source and CO 2 -emissions, Electricity supply, Energy imports by country of origin in January-June 2000, Energy exports by recipient country in January-June 2000, Consumer prices of liquid fuels, Consumer prices of hard coal, natural gas and indigenous fuels, Average electricity price by type of consumer, Price of district heating by type of consumer, Excise taxes, value added taxes and fiscal charges and fees included in consumer prices of some energy sources and Energy taxes and precautionary stock fees on oil products

  20. 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)

  1. 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

  2. To the problem of the statistical basis of evaluation of the mechanical safety factor

    International Nuclear Information System (INIS)

    Tsyganov, S.V.

    2009-01-01

    The methodology applied for the safety factor assessment of the WWER fuel cycles uses methods and terms of statistics. Value of the factor is calculated on the basis of estimation of probability to meet predefined limits. Such approach demands the special attention to the statistical properties of parameters of interest. Considering the mechanical constituents of the engineering factor it is assumed uncertainty factors of safety parameters are stochastic values. It characterized by probabilistic distributions that can be unknown. Traditionally in the safety factor assessment process the unknown parameters are estimated from the conservative points of view. This paper analyses how the refinement of the factors distribution parameters is important for the assessment of the mechanical safety factor. For the analysis the statistical approach is applied for modelling of different type of factor probabilistic distributions. It is shown the significant influence of the shape and parameters of distributions for some factors on the value of mechanical safety factor. (Authors)

  3. To the problem of the statistical basis of evaluation of the mechanical safety factor

    International Nuclear Information System (INIS)

    Tsyganov, S.

    2009-01-01

    The methodology applied for the safety factor assessment of the VVER fuel cycles uses methods and terms of statistics. Value of the factor is calculated on the basis of estimation of probability to meet predefined limits. Such approach demands the special attention to the statistical properties of parameters of interest. Considering the mechanical constituents of the engineering factor it is assumed uncertainty factors of safety parameters are stochastic values. It characterized by probabilistic distributions that can be unknown. Traditionally in the safety factor assessment process the unknown parameters are estimated from the conservative points of view. This paper analyses how the refinement of the factors distribution parameters is important for the assessment of the mechanical safety factor. For the analysis the statistical approach is applied for modelling of different type of factor probabilistic distributions. It is shown the significant influence of the shape and parameters of distributions for some factors on the value of mechanical safety factor. (author)

  4. 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...

  5. 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...

  6. 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)

  7. 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.)

  8. 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.

  9. 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

  10. Sources of Safety Data and Statistical Strategies for Design and Analysis: Clinical Trials.

    Science.gov (United States)

    Zink, Richard C; Marchenko, Olga; Sanchez-Kam, Matilde; Ma, Haijun; Jiang, Qi

    2018-03-01

    There has been an increased emphasis on the proactive and comprehensive evaluation of safety endpoints to ensure patient well-being throughout the medical product life cycle. In fact, depending on the severity of the underlying disease, it is important to plan for a comprehensive safety evaluation at the start of any development program. Statisticians should be intimately involved in this process and contribute their expertise to study design, safety data collection, analysis, reporting (including data visualization), and interpretation. In this manuscript, we review the challenges associated with the analysis of safety endpoints and describe the safety data that are available to influence the design and analysis of premarket clinical trials. We share our recommendations for the statistical and graphical methodologies necessary to appropriately analyze, report, and interpret safety outcomes, and we discuss the advantages and disadvantages of safety data obtained from clinical trials compared to other sources. Clinical trials are an important source of safety data that contribute to the totality of safety information available to generate evidence for regulators, sponsors, payers, physicians, and patients. This work is a result of the efforts of the American Statistical Association Biopharmaceutical Section Safety Working Group.

  11. Sources of Safety Data and Statistical Strategies for Design and Analysis: Transforming Data Into Evidence.

    Science.gov (United States)

    Ma, Haijun; Russek-Cohen, Estelle; Izem, Rima; Marchenko, Olga V; Jiang, Qi

    2018-03-01

    Safety evaluation is a key aspect of medical product development. It is a continual and iterative process requiring thorough thinking, and dedicated time and resources. In this article, we discuss how safety data are transformed into evidence to establish and refine the safety profile of a medical product, and how the focus of safety evaluation, data sources, and statistical methods change throughout a medical product's life cycle. Some challenges and statistical strategies for medical product safety evaluation are discussed. Examples of safety issues identified in different periods, that is, premarketing and postmarketing, are discussed to illustrate how different sources are used in the safety signal identification and the iterative process of safety assessment. The examples highlighted range from commonly used pediatric vaccine given to healthy children to medical products primarily used to treat a medical condition in adults. These case studies illustrate that different products may require different approaches, and once a signal is discovered, it could impact future safety assessments. Many challenges still remain in this area despite advances in methodologies, infrastructure, public awareness, international harmonization, and regulatory enforcement. Innovations in safety assessment methodologies are pressing in order to make the medical product development process more efficient and effective, and the assessment of medical product marketing approval more streamlined and structured. Health care payers, providers, and patients may have different perspectives when weighing in on clinical, financial and personal needs when therapies are being evaluated.

  12. 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.

  13. 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.)

  14. Study on Semi-Parametric Statistical Model of Safety Monitoring of Cracks in Concrete Dams

    Directory of Open Access Journals (Sweden)

    Chongshi Gu

    2013-01-01

    Full Text Available Cracks are one of the hidden dangers in concrete dams. The study on safety monitoring models of concrete dam cracks has always been difficult. Using the parametric statistical model of safety monitoring of cracks in concrete dams, with the help of the semi-parametric statistical theory, and considering the abnormal behaviors of these cracks, the semi-parametric statistical model of safety monitoring of concrete dam cracks is established to overcome the limitation of the parametric model in expressing the objective model. Previous projects show that the semi-parametric statistical model has a stronger fitting effect and has a better explanation for cracks in concrete dams than the parametric statistical model. However, when used for forecast, the forecast capability of the semi-parametric statistical model is equivalent to that of the parametric statistical model. The modeling of the semi-parametric statistical model is simple, has a reasonable principle, and has a strong practicality, with a good application prospect in the actual project.

  15. 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...

  16. Methods for estimating flow-duration and annual mean-flow statistics for ungaged streams in Oklahoma

    Science.gov (United States)

    Esralew, Rachel A.; Smith, S. Jerrod

    2010-01-01

    Flow statistics can be used to provide decision makers with surface-water information needed for activities such as water-supply permitting, flow regulation, and other water rights issues. Flow statistics could be needed at any location along a stream. Most often, streamflow statistics are needed at ungaged sites, where no flow data are available to compute the statistics. Methods are presented in this report for estimating flow-duration and annual mean-flow statistics for ungaged streams in Oklahoma. Flow statistics included the (1) annual (period of record), (2) seasonal (summer-autumn and winter-spring), and (3) 12 monthly duration statistics, including the 20th, 50th, 80th, 90th, and 95th percentile flow exceedances, and the annual mean-flow (mean of daily flows for the period of record). Flow statistics were calculated from daily streamflow information collected from 235 streamflow-gaging stations throughout Oklahoma and areas in adjacent states. A drainage-area ratio method is the preferred method for estimating flow statistics at an ungaged location that is on a stream near a gage. The method generally is reliable only if the drainage-area ratio of the two sites is between 0.5 and 1.5. Regression equations that relate flow statistics to drainage-basin characteristics were developed for the purpose of estimating selected flow-duration and annual mean-flow statistics for ungaged streams that are not near gaging stations on the same stream. Regression equations were developed from flow statistics and drainage-basin characteristics for 113 unregulated gaging stations. Separate regression equations were developed by using U.S. Geological Survey streamflow-gaging stations in regions with similar drainage-basin characteristics. These equations can increase the accuracy of regression equations used for estimating flow-duration and annual mean-flow statistics at ungaged stream locations in Oklahoma. Streamflow-gaging stations were grouped by selected drainage

  17. 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...

  18. Sources of Safety Data and Statistical Strategies for Design and Analysis: Postmarket Surveillance.

    Science.gov (United States)

    Izem, Rima; Sanchez-Kam, Matilde; Ma, Haijun; Zink, Richard; Zhao, Yueqin

    2018-03-01

    Safety data are continuously evaluated throughout the life cycle of a medical product to accurately assess and characterize the risks associated with the product. The knowledge about a medical product's safety profile continually evolves as safety data accumulate. This paper discusses data sources and analysis considerations for safety signal detection after a medical product is approved for marketing. This manuscript is the second in a series of papers from the American Statistical Association Biopharmaceutical Section Safety Working Group. We share our recommendations for the statistical and graphical methodologies necessary to appropriately analyze, report, and interpret safety outcomes, and we discuss the advantages and disadvantages of safety data obtained from passive postmarketing surveillance systems compared to other sources. Signal detection has traditionally relied on spontaneous reporting databases that have been available worldwide for decades. However, current regulatory guidelines and ease of reporting have increased the size of these databases exponentially over the last few years. With such large databases, data-mining tools using disproportionality analysis and helpful graphics are often used to detect potential signals. Although the data sources have many limitations, analyses of these data have been successful at identifying safety signals postmarketing. Experience analyzing these dynamic data is useful in understanding the potential and limitations of analyses with new data sources such as social media, claims, or electronic medical records data.

  19. Educating America's Workforce: Summary of Key Operating Statistics. Data collected from the 2007 and 2008 Annual Institutional Reports

    Science.gov (United States)

    Accrediting Council for Independent Colleges and Schools, 2009

    2009-01-01

    This special edition of the Key Operating Statistics (KOS) contains information based on the 2007 and 2008 Annual Institutional Reports (AIR) submitted by ACICS-accredited institutions. The AIR is submitted on September 15 each year by ACICS-accredited institutions. It reflects activity during a reporting year that begins on July 1 and concludes…

  20. Oberbergamt fuer das Saarland und das Land Rheinland-Pfalz, Bergamt Saarbruecken/Bergamt Rheinland-Pfalz. Annual report 1999. Economic and technical aspects, industrial safety and environmental protection, statistics, activities of the mining authorities; Oberbergamt fuer das Saarland und das Land Rheinland-Pfalz, Bergamt Saarbruecken/Bergamt Rheinland-Pfalz. Jahresbericht 1999.. Bergwirtschaft, Bergtechnik, Arbeitsschutz, Umweltschutz, Statistiken, Taetigkeiten der Bergbehoerden

    Energy Technology Data Exchange (ETDEWEB)

    Boettcher, R.; Hugo, K.H.; Kuhn, M.; Strauch, T. (comps.)

    1999-07-01

    The developments in Saarland and Rhineland-Palatinate mining are presented. Structure and responsibilities of the regional mines inspectorate are described, and their activities in the following fields are reported: industrial safety, health, mining and safety, mining and environmental protection. (orig.) [German] Nach Darstellung der bergwirtschaftlichen Entwicklung im Saarland und im Land Rheinland-Pfalz wird ueber den Aufbau und die Zustaendigkeit der Bergbehoerden sowie ueber deren Taetigkeiten auf folgenden Gebieten berichtet: Arbeits- und Gesundheitsschutz, Bergtechnik und Sicherheit, Bergbau und Umwelt. (orig.)

  1. 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

  2. Application of a statistical thermal design procedure to evaluate the PWR DNBR safety analysis limits

    International Nuclear Information System (INIS)

    Robeyns, J.; Parmentier, F.; Peeters, G.

    2001-01-01

    In the framework of safety analysis for the Belgian nuclear power plants and for the reload compatibility studies, Tractebel Energy Engineering (TEE) has developed, to define a 95/95 DNBR criterion, a statistical thermal design method based on the analytical full statistical approach: the Statistical Thermal Design Procedure (STDP). In that methodology, each DNBR value in the core assemblies is calculated with an adapted CHF (Critical Heat Flux) correlation implemented in the sub-channel code Cobra for core thermal hydraulic analysis. The uncertainties of the correlation are represented by the statistical parameters calculated from an experimental database. The main objective of a sub-channel analysis is to prove that in all class 1 and class 2 situations, the minimum DNBR (Departure from Nucleate Boiling Ratio) remains higher than the Safety Analysis Limit (SAL). The SAL value is calculated from the Statistical Design Limit (SDL) value adjusted with some penalties and deterministic factors. The search of a realistic value for the SDL is the objective of the statistical thermal design methods. In this report, we apply a full statistical approach to define the DNBR criterion or SDL (Statistical Design Limit) with the strict observance of the design criteria defined in the Standard Review Plan. The same statistical approach is used to define the expected number of rods experiencing DNB. (author)

  3. 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

  4. Saarland and Rheinland-Pfalz Mines Inspectorate. Annual report 1996. Economic and technical aspects, industrial safety and environmental protection, statistics, activities of the mining authorities; Oberbergamt fuer das Saarland und das Land Rheinland-Pfalz. Jahresbericht 1996. Bergwirtschaft, Bergtechnik, Arbeitsschutz, Umweltschutz, Statistiken, Taetigkeiten der Bergbehoerden

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The annual report of the Saarland and Rheinland-Pfalz Mines Inspectorate outlines the economic and technical developments in mining in these two German states as well as the activities of the mining authorities in all fields of mining. (orig.) [Deutsch] Der Jahresbericht des Oberbergamtes fuer das Saarland und das Land Rheinland-Pfalz gibt einen Ueberblick zur bergwirtschaftlichen und bergtechnischen Entwicklung in beiden Bundeslaendern und vermittelt einen umfassenden Einblick in die Taetigkeiten der Bergbehoerden in den vielfaeltigen Bergbauzweigen. (orig.)

  5. 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

  6. 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

  7. 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

  8. 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)

  9. 36 CFR 902.12 - Maintenance of statistics; annual report to Congress.

    Science.gov (United States)

    2010-07-01

    ...; annual report to Congress. 902.12 Section 902.12 Parks, Forests, and Public Property PENNSYLVANIA AVENUE...; annual report to Congress. (a) The Administrative Officer shall maintain records of: (1) The fees... committees of Congress. [41 FR 43143, Sept. 30, 1976, as amended at 48 FR 17354, Apr. 22, 1983] ...

  10. 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

  11. 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.)

  12. 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.)

  13. 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.

  14. 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.

  15. Drug safety data mining with a tree-based scan statistic.

    Science.gov (United States)

    Kulldorff, Martin; Dashevsky, Inna; Avery, Taliser R; Chan, Arnold K; Davis, Robert L; Graham, David; Platt, Richard; Andrade, Susan E; Boudreau, Denise; Gunter, Margaret J; Herrinton, Lisa J; Pawloski, Pamala A; Raebel, Marsha A; Roblin, Douglas; Brown, Jeffrey S

    2013-05-01

    In post-marketing drug safety surveillance, data mining can potentially detect rare but serious adverse events. Assessing an entire collection of drug-event pairs is traditionally performed on a predefined level of granularity. It is unknown a priori whether a drug causes a very specific or a set of related adverse events, such as mitral valve disorders, all valve disorders, or different types of heart disease. This methodological paper evaluates the tree-based scan statistic data mining method to enhance drug safety surveillance. We use a three-million-member electronic health records database from the HMO Research Network. Using the tree-based scan statistic, we assess the safety of selected antifungal and diabetes drugs, simultaneously evaluating overlapping diagnosis groups at different granularity levels, adjusting for multiple testing. Expected and observed adverse event counts were adjusted for age, sex, and health plan, producing a log likelihood ratio test statistic. Out of 732 evaluated disease groupings, 24 were statistically significant, divided among 10 non-overlapping disease categories. Five of the 10 signals are known adverse effects, four are likely due to confounding by indication, while one may warrant further investigation. The tree-based scan statistic can be successfully applied as a data mining tool in drug safety surveillance using observational data. The total number of statistical signals was modest and does not imply a causal relationship. Rather, data mining results should be used to generate candidate drug-event pairs for rigorous epidemiological studies to evaluate the individual and comparative safety profiles of drugs. Copyright © 2013 John Wiley & Sons, Ltd.

  16. State Mines Inspectorate of Saarland and Rheinland-Pfalz, Mines InspectorateSaarbruecken/ Mines Inspectorate Rheinland-Pfalz. Annual report 2000. Economic and technical aspects, industrial safety and enviromental protection, statistics, activities of the mining authorities; Oberbergamt fuer das Saarland und das Land Rheinland-Pfalz, Bergamt Saarbruecken/Bergamt Rheinland-Pfalz. Jahresbericht 2000. Bergwirtschaft, Bergtechnik, Arbeitsschutz, Umweltschutz, Statistiken, Taetigkeiten der Bergbehoerden

    Energy Technology Data Exchange (ETDEWEB)

    Boettcher, R.; Hugo, K.H.; Kuhn, M.; Strauch, T. (comps.)

    2001-07-01

    The annual report of the Saarland and Rheinland-Pfalz State Mines Inspectorate and the Mines Inspectorates of the two states provide an insight into the many activities of mines inspectorates and of the current trends in mining engineering. The importance of mining and regional raw materials management is stressed. [German] Der vorliegende Jahresbericht des Oberbergamtes fuer das Saarland und das Land Rheinland-Pfalz sowie der Bergaemter in beiden Bundeslaendern gibt einen Einblick in das vielfaeltige Arbeitsgebiet der Bergbehoerden. Gleichzeitig vermittelt er einen Ueberblick ueber die bergtechnische Entwicklung und unterstreicht die volkswirtschaftliche Bedeutung des Bergbaus und der standortgebundenen Rohstoffwirtschaft. (orig.)

  17. State Mines Inspectorate of Saarland and Rheinland-Pfalz, Mines Inspectorate Saarbruecken / Mines Inspectorate Rheinland-Pfalz. Annual report 2001. Economic and technical aspects, industrial safety and environmental protection, statistics, activities of the mining authorities; Oberbergamt fuer das Saarland und das Land Rheinland-Pfalz, Bergamt Saarbruecken / Bergamt Rheinland-Pfalz. Jahresbericht 2001. Bergwirtschaft, Bergtechnik, Arbeitsschutz, Umweltschutz, Statistiken, Taetigkeiten der Bergbehoerden

    Energy Technology Data Exchange (ETDEWEB)

    Boettcher, R.; Hugo, K.H.; Kuhn, M.; Strauch, T. (comps.)

    2002-07-01

    The annual report of the Saarland and Rheinland-Pfalz State Mines Inspectorate and the Mines Inspectorates of the two states provide an insight into the many activities of mines inspectorates and of the current trends in mining engineering. The importance of mining and regional raw materials management is stressed. [German] Der vorliegende Jahresbericht des Oberbergamtes fuer das Saarland und das Land Rheinland-Pfalz sowie der Bergaemter in beiden Bundeslaendern gibt einen Einblick in das vielfaeltige Arbeitsgebiet der Bergbehoerden. Gleichzeitig vermittelt er einen Ueberblick ueber die bergtechnische Entwicklung und unterstreicht die volkswirtschaftliche Bedeutung des Bergbaus und der standortgebundenen Rohstoffwirtschaft.

  18. Compliance strategy for statistically based neutron overpower protection safety analysis methodology

    International Nuclear Information System (INIS)

    Holliday, E.; Phan, B.; Nainer, O.

    2009-01-01

    The methodology employed in the safety analysis of the slow Loss of Regulation (LOR) event in the OPG and Bruce Power CANDU reactors, referred to as Neutron Overpower Protection (NOP) analysis, is a statistically based methodology. Further enhancement to this methodology includes the use of Extreme Value Statistics (EVS) for the explicit treatment of aleatory and epistemic uncertainties, and probabilistic weighting of the initial core states. A key aspect of this enhanced NOP methodology is to demonstrate adherence, or compliance, with the analysis basis. This paper outlines a compliance strategy capable of accounting for the statistical nature of the enhanced NOP methodology. (author)

  19. Statistical attribution analysis of the nonstationarity of the annual runoff series of the Weihe River.

    Science.gov (United States)

    Xiong, Lihua; Jiang, Cong; Du, Tao

    2014-01-01

    Time-varying moments models based on Pearson Type III and normal distributions respectively are built under the generalized additive model in location, scale and shape (GAMLSS) framework to analyze the nonstationarity of the annual runoff series of the Weihe River, the largest tributary of the Yellow River. The detection of nonstationarities in hydrological time series (annual runoff, precipitation and temperature) from 1960 to 2009 is carried out using a GAMLSS model, and then the covariate analysis for the annual runoff series is implemented with GAMLSS. Finally, the attribution of each covariate to the nonstationarity of annual runoff is analyzed quantitatively. The results demonstrate that (1) obvious change-points exist in all three hydrological series, (2) precipitation, temperature and irrigated area are all significant covariates of the annual runoff series, and (3) temperature increase plays the main role in leading to the reduction of the annual runoff series in the study basin, followed by the decrease of precipitation and the increase of irrigated area.

  20. 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

  1. Annual bulletin of coal statistics for Europe. [1970 to 1975; by country; Europe plus USA and Canada; no text

    Energy Technology Data Exchange (ETDEWEB)

    1975-01-01

    The purpose of this report is to provide basic data on developments and trends in the field of solid fuels in European countries, Canada and the United States of America. The data refer to production, stocks, inland availabilities, deliveries, trade, employment, and labour productivity. The Annual Bulletin is supplemented by a Quarterly Bulletin of Coal Statistics for Europe which contains monthly data on production, trade, stocks and inland availabilities. Both publications are purely statistical in character. For an analysis of the coal situation and its prospects, reference may be made to the periodic reviews prepared by the secretariat of the United Nations Economic Commission for Europe.

  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. A statistical analysis of the impact of advertising signs on road safety.

    Science.gov (United States)

    Yannis, George; Papadimitriou, Eleonora; Papantoniou, Panagiotis; Voulgari, Chrisoula

    2013-01-01

    This research aims to investigate the impact of advertising signs on road safety. An exhaustive review of international literature was carried out on the effect of advertising signs on driver behaviour and safety. Moreover, a before-and-after statistical analysis with control groups was applied on several road sites with different characteristics in the Athens metropolitan area, in Greece, in order to investigate the correlation between the placement or removal of advertising signs and the related occurrence of road accidents. Road accident data for the 'before' and 'after' periods on the test sites and the control sites were extracted from the database of the Hellenic Statistical Authority, and the selected 'before' and 'after' periods vary from 2.5 to 6 years. The statistical analysis shows no statistical correlation between road accidents and advertising signs in none of the nine sites examined, as the confidence intervals of the estimated safety effects are non-significant at 95% confidence level. This can be explained by the fact that, in the examined road sites, drivers are overloaded with information (traffic signs, directions signs, labels of shops, pedestrians and other vehicles, etc.) so that the additional information load from advertising signs may not further distract them.

  8. Line-robust statistics for continuous gravitational waves: safety in the case of unequal detector sensitivities

    International Nuclear Information System (INIS)

    Keitel, David; Prix, Reinhard

    2015-01-01

    The multi-detector F-statistic is close to optimal for detecting continuous gravitational waves (CWs) in Gaussian noise. However, it is susceptible to false alarms from instrumental artefacts, for example quasi-monochromatic disturbances (‘lines’), which resemble a CW signal more than Gaussian noise. In a recent paper (Keitel et al 2014 Phys. Rev. D 89 064023), a Bayesian model selection approach was used to derive line-robust detection statistics for CW signals, generalizing both the F-statistic and the F-statistic consistency veto technique and yielding improved performance in line-affected data. Here we investigate a generalization of the assumptions made in that paper: if a CW analysis uses data from two or more detectors with very different sensitivities, the line-robust statistics could be less effective. We investigate the boundaries within which they are still safe to use, in comparison with the F-statistic. Tests using synthetic draws show that the optimally-tuned version of the original line-robust statistic remains safe in most cases of practical interest. We also explore a simple idea on further improving the detection power and safety of these statistics, which we, however, find to be of limited practical use. (paper)

  9. 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.)

  10. 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

  11. 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

  12. European downstream oil industry safety performance. Statistical summary of reported incidents 2009

    International Nuclear Information System (INIS)

    Burton, A.; Den Haan, K.H.

    2010-10-01

    The sixteenth such report by CONCAWE, this issue includes statistics on workrelated personal injuries for the European downstream oil industry's own employees as well as contractors for the year 2009. Data were received from 33 companies representing more than 97% of the European refining capacity. Trends over the last sixteen years are highlighted and the data are also compared to similar statistics from related industries. In addition, this report presents the results of the first Process Safety Performance Indicator data gathering exercise amongst the CONCAWE membership.

  13. 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

  14. Statistics

    CERN Document Server

    Hayslett, H T

    1991-01-01

    Statistics covers the basic principles of Statistics. The book starts by tackling the importance and the two kinds of statistics; the presentation of sample data; the definition, illustration and explanation of several measures of location; and the measures of variation. The text then discusses elementary probability, the normal distribution and the normal approximation to the binomial. Testing of statistical hypotheses and tests of hypotheses about the theoretical proportion of successes in a binomial population and about the theoretical mean of a normal population are explained. The text the

  15. Estimating long-term statistics for annual precipitation for six regions of the United States from tree-ring data

    International Nuclear Information System (INIS)

    Fritts, H.C.; DeWitt, E.; Gordon, G.A.; Hunt, J.H.; Lofgren, G.R.

    1979-12-01

    Spatial anomalies of seasonal precipitation for the United States and southwestern Canada have been reconstructed from 1602 through 1961 using dendrochronological and multivariate techniques on 65 arid-site tree-ring chronologies from western North America. Seasonal reconstructions are averaged to obtain mean annual precipitation values for six regions of importance to the Nuclear Regulatory Commission (NRC) Nuclear Waste Management Program (NWMP). Statistics calculated from the regionally averaged annual values for 25-year and longer intervals show annual precipitation in the seventeenth through nineteenth centuries to be lower than in the twentieth century for three regions in the American Southwest and higher for one region in the Northwest and two regions in the East. The variability of precipitation generally was higher in the past three centuries than in the present century. Twenty-five-year intervals with noteworthy statistics are identified and important results are summarized and tabulated for use in the hydrologic modeling of the NWMP. Additional research is recommended to incorporate temperature and precipitation into a single hydrologic parameter

  16. 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.)

  17. Annual mean statistics of the surface fluxes of the tropical Indian Ocean

    Digital Repository Service at National Institute of Oceanography (India)

    RameshKumar, M.R.; Rao, L.V.G.

    MEAN STATISTICS OF THE SURFACE FLUXES OF THE TROPICAL INDIAN OCEAN (Research Note) M. R. RAMESH KUMAR and L. V. GANGADHARA RAO Physical Oceanography Division, National Institute of Oceanography, Dona Paula, 403004, Goa, India (Received in final...

  18. Two decades of change in transportation reflections from transportation statistics annual reports 1994–2014.

    Science.gov (United States)

    2015-01-01

    The Bureau of Transportation Statistics (BTS) provides information to support understanding and decision-making related to the transportation system, including the size and extent of the system, how it is used, how well it works, and its contribution...

  19. Statistics

    Science.gov (United States)

    Links to sources of cancer-related statistics, including the Surveillance, Epidemiology and End Results (SEER) Program, SEER-Medicare datasets, cancer survivor prevalence data, and the Cancer Trends Progress Report.

  20. Annual rainfall statistics for stations in the Top End of Australia: normal and log-normal distribution analysis

    International Nuclear Information System (INIS)

    Vardavas, I.M.

    1992-01-01

    A simple procedure is presented for the statistical analysis of measurement data where the primary concern is the determination of the value corresponding to a specified average exceedance probability. The analysis employs the normal and log-normal frequency distributions together with a χ 2 -test and an error analysis. The error analysis introduces the concept of a counting error criterion, or ζ-test, to test whether the data are sufficient to make the Z 2 -test reliable. The procedure is applied to the analysis of annual rainfall data recorded at stations in the tropical Top End of Australia where the Ranger uranium deposit is situated. 9 refs., 12 tabs., 9 figs

  1. Understanding Statistics - Cancer Statistics

    Science.gov (United States)

    Annual reports of U.S. cancer statistics including new cases, deaths, trends, survival, prevalence, lifetime risk, and progress toward Healthy People targets, plus statistical summaries for a number of common cancer types.

  2. 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)

  3. 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)

  4. 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.

  5. Annual Bulletin of General Energy Statistics for Europe. V. 23, 1990

    International Nuclear Information System (INIS)

    1992-01-01

    The purpose of the Bulletin is to provide basic data on the energy situation as a whole in European countries, Canada and the United States of America. This publication is purely statistical in character. As from the 1980 edition of the bulletin the scope of statistics comprises production of energy by form, overall energy balance sheets and deliveries of petroleum products for inland consumption. While less details are given for solid and gaseous fuels as sources of energy than in previous editions of the bulletin, more information is available for liquid fuels and nuclear, hydro- and geothermal energy

  6. Statistical annual report 2008 - Furnas Electric Power Plants Inc. - Calendar year 2007; Anuario estatistico 2008 - Furnas Centrais Eletricas S.A. - Ano base 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This 30th edition of the statistical annual report of Furnas reports the performance of the company in 2007 and recent years allowing a general view on: Furnas system; production and supply; financial and economic data, personnel and indicators.

  7. Brazilian energy statistics - 1996. Annual bulletin of the Brazilian Committee of the World Energy Council

    International Nuclear Information System (INIS)

    1996-01-01

    This bulletin deals with the primary sources that carry most weight in the Brazilian energy balance: hydroelectric energy, petroleum, natural gas and coal. It also contains data on ethyl alcohol derived of sugar cane since it is of special importance in Brazil's energy scenario. Domestic production, petroleum and petroleum product imports, as well as natural gas production statistics are furnished in this bulletin

  8. 78 FR 13072 - Seventh Annual Drug Information Association/Food and Drug Administration Statistics Forum-2013...

    Science.gov (United States)

    2013-02-26

    ... establish an ongoing dialogue regarding FDA's ``Critical Path'' initiative--emphasizing the regulatory and... application of statistical methodologies and thinking to the development of new therapeutic biologics and... improving the communication between industry statisticians and FDA reviewers. A description of the planned...

  9. 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

  10. The Association of Academic Health Sciences Libraries Annual Statistics: an exploratory twenty-five-year trend analysis.

    Science.gov (United States)

    Byrd, Gary D; Shedlock, James

    2003-04-01

    This paper presents an exploratory trend analysis of the statistics published over the past twenty-four editions of the Annual Statistics of Medical School Libraries in the United States and Canada. The analysis focuses on the small subset of nineteen consistently collected data variables (out of 656 variables collected during the history of the survey) to provide a general picture of the growth and changing dimensions of services and resources provided by academic health sciences libraries over those two and one-half decades. The paper also analyzes survey response patterns for U.S. and Canadian medical school libraries, as well as osteopathic medical school libraries surveyed since 1987. The trends show steady, but not dramatic, increases in annual means for total volumes collected, expenditures for staff, collections and other operating costs, personnel numbers and salaries, interlibrary lending and borrowing, reference questions, and service hours. However, when controlled for inflation, most categories of expenditure have just managed to stay level. The exceptions have been expenditures for staff development and travel and for collections, which have both outpaced inflation. The fill rate for interlibrary lending requests has remained steady at about 75%, but the mean ratio of items lent to items borrowed has decreased by nearly 50%.

  11. 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.)

  12. Co-ordinated Research Projects (CRPs): Annual report of activities and statistics for 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-15

    Article III of the IAEA Statute authorises the Agency to encourage and assist research on, and development and practical application of, atomic energy for peaceful purposes throughout the world and to foster the exchange of scientific and technical information, as well as the exchange of scientists in the field of peaceful uses of atomic energy. The research supported by the Agency is within the framework of the Agency's programmes, sub-programmes and projects that are listed in the approved Programme and Budget of the Agency. The research work is normally implemented through Coordinated Research Projects (CRPs) that bring together research institutes in both developing and developed Member States to collaborate on the research topic of interest. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear technologies in developing Member States through CRPs that rest on pair building between agreement holders and contract holders and includes a PhD training programme at the contract holders' institutions. Further details of the administration of research contracts and general information on CRPs is contained in the Agency?s Website at http://www.iaea.org/programmes/ri/uc.html. The CRPs reported in this document are conducted in support of the following Agency programmes: 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. The Sub-programmes supported by the CRPs are listed. Results of research are available to all Member States, and are disseminated through national

  13. Co-ordinated Research Projects (CRPs): Annual report of activities and statistics for 2001

    International Nuclear Information System (INIS)

    2002-07-01

    Article III of the IAEA Statute authorises the Agency to encourage and assist research on, and development and practical application of, atomic energy for peaceful purposes throughout the world and to foster the exchange of scientific and technical information, as well as the exchange of scientists in the field of peaceful uses of atomic energy. The research supported by the Agency is within the framework of the Agency's programmes, sub-programmes and projects that are listed in the approved Programme and Budget of the Agency. The research work is normally implemented through Coordinated Research Projects (CRPs) that bring together research institutes in both developing and developed Member States to collaborate on the research topic of interest. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear technologies in developing Member States through CRPs that rest on pair building between agreement holders and contract holders and includes a PhD training programme at the contract holders' institutions. Further details of the administration of research contracts and general information on CRPs is contained in the Agency?s Website at http://www.iaea.org/programmes/ri/uc.html. The CRPs reported in this document are conducted in support of the following Agency programmes: 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. The Sub-programmes supported by the CRPs are listed. Results of research are available to all Member States, and are disseminated through national

  14. Mourning dove hunting regulation strategy based on annual harvest statistics and banding data

    Science.gov (United States)

    Otis, D.L.

    2006-01-01

    Although managers should strive to base game bird harvest management strategies on mechanistic population models, monitoring programs required to build and continuously update these models may not be in place. Alternatively, If estimates of total harvest and harvest rates are available, then population estimates derived from these harvest data can serve as the basis for making hunting regulation decisions based on population growth rates derived from these estimates. I present a statistically rigorous approach for regulation decision-making using a hypothesis-testing framework and an assumed framework of 3 hunting regulation alternatives. I illustrate and evaluate the technique with historical data on the mid-continent mallard (Anas platyrhynchos) population. I evaluate the statistical properties of the hypothesis-testing framework using the best available data on mourning doves (Zenaida macroura). I use these results to discuss practical implementation of the technique as an interim harvest strategy for mourning doves until reliable mechanistic population models and associated monitoring programs are developed.

  15. Monitoring and Evaluation; Statistical Support for Life-cycle Studies, 2003 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Skalski, John

    2003-12-01

    This report summarizes the statistical analysis and consulting activities performed under Contract No. 00004134, Project No. 199105100 funded by Bonneville Power Administration during 2003. These efforts are focused on providing real-time predictions of outmigration timing, assessment of life-history performance measures, evaluation of status and trends in recovery, and guidance on the design and analysis of Columbia Basin fish and wildlife studies monitoring and evaluation studies. The overall objective of the project is to provide BPA and the rest of the fisheries community with statistical guidance on design, analysis, and interpretation of monitoring data, which will lead to improved monitoring and evaluation of salmonid mitigation programs in the Columbia/Snake River Basin. This overall goal is being accomplished by making fisheries data readily available for public scrutiny, providing statistical guidance on the design and analyses of studies by hands-on support and written documents, and providing real-time analyses of tagging results during the smolt outmigration for review by decision makers. For a decade, this project has been providing in-season projections of smolt outmigration timing to assist in spill management. As many as 50 different fish stocks at 8 different hydroprojects are tracked and real-time to predict the 'percent of run to date' and 'date to specific percentile'. The project also conducts added-value analyses of historical tagging data to understand relationships between fish responses, environmental factors, and anthropogenic effects. The statistical analysis of historical tagging data crosses agency lines in order to assimilate information on salmon population dynamics irrespective of origin. The lessons learned from past studies are used to improve the design and analyses of future monitoring and evaluation efforts. Through these efforts, the project attempts to provide the fisheries community with reliable analyses

  16. Statistical Analysis of the Worker Engagement Survey Administered at the Worker Safety and Security Team Festival

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Adam Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-08-25

    The Worker Safety and Security Team (WSST) at Los Alamos National Laboratory holds an annual festival, WSST-fest, to engage workers and inform them about safety- and securityrelated matters. As part of the 2015 WSST-fest, workers were given the opportunity to participate in a survey assessing their engagement in their organizations and work environments. A total of 789 workers participated in the 23-question survey where they were also invited, optionally, to identify themselves, their organization, and to give open-ended feedback. The survey consisted of 23 positive statements (i.e. “My organization is a good place to work.”) with which the respondent could express a level of agreement. The text of these statements are provided in Table 1. The level of agreement corresponds to a 5-level Likert scale ranging from “Strongly Disagree” to “Strongly Agree.” In addition to assessing the overall positivity or negativity of the scores, the results were partitioned into several cohorts based on the response meta-data (self-identification, comments, etc.) to explore trends. Survey respondents were presented with the options to identify themselves, their organizations and to provide comments. These options suggested the following questions about the data set.

  17. 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.

  18. Co-ordinated research activities: Annual report and statistics for 2003

    International Nuclear Information System (INIS)

    2004-07-01

    Energy Development; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation Safety (including Transport Safety); Management of Radioactive Waste; Safeguards; Security of Material. Results of research are available to all Member States, and are disseminated through national, international and Agency scientific and technical publications (TECDOCs). In certain cases the research results are directly relevant to implementation of projects in the Agency's Technical Co-operation Programme. In terms of benefits to Member States through their participating research institutions, number of awards and degree of funding, co-ordinated research activities constitute a significant component of the Agency's overall programme. 883 contracts and agreements were awarded from the 1242 contract and agreement proposals received by the Agency during 2003. Annex I lists by country the number of proposals received and awards made. In 2003, $6 675 465 were awarded from the regular budget to institutes under contractual arrangements and to fund Research Co-ordination Meetings (RCMs). Additionally, $325 546 of extra-budgetary contributions were used to fund additional contracts and RCMs. Thus, total awards amounted to $7 001 011. Table 1 summarizes all awards by Programme in 2003. The average award per contract rose to $6 400, which represents a 12% increase over the 2002 average award level

  19. Co-ordinated research activities: Annual report and statistics for 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-15

    Energy Development; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation Safety (including Transport Safety); Management of Radioactive Waste; Safeguards; Security of Material. Results of research are available to all Member States, and are disseminated through national, international and Agency scientific and technical publications (TECDOCs). In certain cases the research results are directly relevant to implementation of projects in the Agency's Technical Co-operation Programme. In terms of benefits to Member States through their participating research institutions, number of awards and degree of funding, co-ordinated research activities constitute a significant component of the Agency's overall programme. 883 contracts and agreements were awarded from the 1242 contract and agreement proposals received by the Agency during 2003. Annex I lists by country the number of proposals received and awards made. In 2003, $6 675 465 were awarded from the regular budget to institutes under contractual arrangements and to fund Research Co-ordination Meetings (RCMs). Additionally, $325 546 of extra-budgetary contributions were used to fund additional contracts and RCMs. Thus, total awards amounted to $7 001 011. Table 1 summarizes all awards by Programme in 2003. The average award per contract rose to $6 400, which represents a 12% increase over the 2002 average award level.

  20. Co-ordinated Research Projects (CRPs): Annual report of activities and statistics for 2002

    International Nuclear Information System (INIS)

    2003-08-01

    Article III of the IAEA Statute authorises the Agency to encourage and assist research on, and development and practical application of, atomic energy for peaceful purposes throughout the world and to foster the exchange of scientific and technical information, as well as the exchange of scientists in the field of peaceful uses of atomic energy. The research supported by the Agency is within the framework of the Agency's programmes, sub-programmes and projects that are listed in the approved Programme and Budget of the Agency. The research work is normally implemented through Coordinated Research Projects (CRPs) that bring together research institutes in both developing and developed Member States to collaborate on the research topic of interest. Doctoral CRPs, (previously known as Thematic CRPs), meant to complement traditional CRPs, are currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear technologies in developing Member States through CRPs that rest on pair building between agreement holders and contract holders and includes a PhD training programme at the contract holders? institutions. Further details of the administration of research contracts and general information on CRPs is contained in the Agency's Website at http://www-crp.iaea.org. The CRPs reported in this document are conducted in support of the following Agency programmes: Nuclear Power; Nuclear Fuel Cycle and Material Technologies; Analysis for Sustainable Energy Development; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation Safety; Management of Radioactive Waste; Safeguards. The Sub-programmes supported by the CRPs are listed. Results of research are available to all Member States, and are disseminated through national, international and Agency scientific

  1. Co-ordinated Research Projects (CRPs): Annual report of activities and statistics for 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-08-15

    Article III of the IAEA Statute authorises the Agency to encourage and assist research on, and development and practical application of, atomic energy for peaceful purposes throughout the world and to foster the exchange of scientific and technical information, as well as the exchange of scientists in the field of peaceful uses of atomic energy. The research supported by the Agency is within the framework of the Agency's programmes, sub-programmes and projects that are listed in the approved Programme and Budget of the Agency. The research work is normally implemented through Coordinated Research Projects (CRPs) that bring together research institutes in both developing and developed Member States to collaborate on the research topic of interest. Doctoral CRPs, (previously known as Thematic CRPs), meant to complement traditional CRPs, are currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear technologies in developing Member States through CRPs that rest on pair building between agreement holders and contract holders and includes a PhD training programme at the contract holders? institutions. Further details of the administration of research contracts and general information on CRPs is contained in the Agency's Website at http://www-crp.iaea.org. The CRPs reported in this document are conducted in support of the following Agency programmes: Nuclear Power; Nuclear Fuel Cycle and Material Technologies; Analysis for Sustainable Energy Development; Nuclear Science; Food and Agriculture; Human Health; Water Resources; Protection of the Marine and Terrestrial Environments; Physical and Chemical Applications; Safety of Nuclear Installations; Radiation Safety; Management of Radioactive Waste; Safeguards. The Sub-programmes supported by the CRPs are listed. Results of research are available to all Member States, and are disseminated through national, international and Agency scientific

  2. 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

  3. 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

  4. 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

  5. Online Dectection and Modeling of Safety Boundaries for Aerospace Application Using Bayesian Statistics

    Science.gov (United States)

    He, Yuning

    2015-01-01

    The behavior of complex aerospace systems is governed by numerous parameters. For safety analysis it is important to understand how the system behaves with respect to these parameter values. In particular, understanding the boundaries between safe and unsafe regions is of major importance. In this paper, we describe a hierarchical Bayesian statistical modeling approach for the online detection and characterization of such boundaries. Our method for classification with active learning uses a particle filter-based model and a boundary-aware metric for best performance. From a library of candidate shapes incorporated with domain expert knowledge, the location and parameters of the boundaries are estimated using advanced Bayesian modeling techniques. The results of our boundary analysis are then provided in a form understandable by the domain expert. We illustrate our approach using a simulation model of a NASA neuro-adaptive flight control system, as well as a system for the detection of separation violations in the terminal airspace.

  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. Statistical assessment of fire safety in multi-residential buildings in Slovenia

    Directory of Open Access Journals (Sweden)

    Domen Kušar

    2009-01-01

    Full Text Available Nearly a third of residential units in Slovenia are located in multi-residential buildings. The majority of such buildings were built after WW2, when the need for suitable accommodation buildings was at its peak. They were built using the construction possibilities and requirements of the time. Every year there are over 200 fires in these buildings, resulting in fatalities and vast material damage. Due to the great efforts over the past centuries, which were all mainly aimed at replacing combustible construction materials with non-combustible ones, and with advancements in fire service equipment and techniques, the number of fires and their scope has decreased significantly but they were not entirely put out. New and greater advances in the field of fire safety of multi-residential buildings became obvious within the last few years, when stricter regulations regarding the construction of such objects came into force. Developments in science and within the industry itself brought about several new solutions in improving the situation in this field, which has been confirmed by experiences from abroad. Unfortunately in Slovenia, the establishment of safety principles still depends mainly on an occupants’ perception, financial means, and at the same time, certain implementation procedures that are much more complicated due to new property ownership. With the aid of the statistical results from the 2002 Census and contemporary fire safety requirements, this article attempts to show the present-day situation of the problem at both the state and municipality level and will propose solutions to improve this situation. The authors established that not even one single older, multi-residential building meets complies with modern requirements. Fortunately, the situation is improved by the fact that most buildings in Slovenia are built from non-combustible materials (concrete, brick, which limit the spread of fire.

  8. 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

  9. 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.

  10. [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

  11. 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.

  12. Bootstrap and Order Statistics for Quantifying Thermal-Hydraulic Code Uncertainties in the Estimation of Safety Margins

    Directory of Open Access Journals (Sweden)

    Enrico Zio

    2008-01-01

    Full Text Available In the present work, the uncertainties affecting the safety margins estimated from thermal-hydraulic code calculations are captured quantitatively by resorting to the order statistics and the bootstrap technique. The proposed framework of analysis is applied to the estimation of the safety margin, with its confidence interval, of the maximum fuel cladding temperature reached during a complete group distribution blockage scenario in a RBMK-1500 nuclear reactor.

  13. 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...

  14. Vital statistics of the union of Myanmar, land use, forest and cover area, annual allowable cut of teak and other hardwoods

    International Nuclear Information System (INIS)

    Sein Maung Wint

    1993-01-01

    Statistical data of net area sown, fallow land, culturable wasteland, reserved forest and forest area (1) by category; (2) by state and division; (3) by forest type; (4) by forest function; (5) by working circle of the Union of Myanmar are shown. Statistical data showing annual allowable cut of teak and other hardwoods by state/division can also be seen. Myanmar forest and woodland area together with other 17 countries of the world are included for comparison

  15. Vital statistics of the union of Myanmar, land use, forest and cover area, annual allowable cut of teak and other hardwoods

    Energy Technology Data Exchange (ETDEWEB)

    Wint, Sein Maung

    1993-10-01

    Statistical data of net area sown, fallow land, culturable wasteland, reserved forest and forest area (1) by category; (2) by state and division; (3) by forest type; (4) by forest function; (5) by working circle of the Union of Myanmar are shown. Statistical data showing annual allowable cut of teak and other hardwoods by state/division can also be seen. Myanmar forest and woodland area together with other 17 countries of the world are included for comparison

  16. 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.

  17. 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)

  18. Development of 4S and related technologies. (3) Statistical evaluation of safety performance of 4S on ULOF event

    International Nuclear Information System (INIS)

    Ishii, Kyoko; Matsumiya, Hisato; Horie, Hideki; Miyagi, Kazumi

    2009-01-01

    The purpose of this work is to evaluate quantitatively and statistically the safety performance of Super-Safe, Small, and Simple reactor (4S) by analyzing with ARGO code, a plant dynamics code for a sodium-cooled fast reactor. In this evaluation, an Anticipated Transient Without Scram (ATWS) is assumed, and an Unprotected Loss of Flow (ULOF) event is selected as a typical ATWS case. After a metric concerned with safety design is defined as performance factor a Phenomena Identification Ranking Table (PIRT) is produced in order to select the plausible phenomena that affect the metric. Then a sensitivity analysis is performed for the parameters related to the selected plausible phenomena. Finally the metric is evaluated with statistical methods whether it satisfies the given safety acceptance criteria. The result is as follows: The Cumulative Damage Fraction (CDF) for the cladding is defined as a metric, and the statistical estimation of the one-sided upper tolerance limit of 95 percent probability at a 95 percent confidence level in CDF is within the safety acceptance criterion; CDF < 0.1. The result shows that the 4S safety performance is acceptable in the ULOF event. (author)

  19. Towards an Industrial Application of Statistical Uncertainty Analysis Methods to Multi-physical Modelling and Safety Analyses

    International Nuclear Information System (INIS)

    Zhang, Jinzhao; Segurado, Jacobo; Schneidesch, Christophe

    2013-01-01

    Since 1980's, Tractebel Engineering (TE) has being developed and applied a multi-physical modelling and safety analyses capability, based on a code package consisting of the best estimate 3D neutronic (PANTHER), system thermal hydraulic (RELAP5), core sub-channel thermal hydraulic (COBRA-3C), and fuel thermal mechanic (FRAPCON/FRAPTRAN) codes. A series of methodologies have been developed to perform and to license the reactor safety analysis and core reload design, based on the deterministic bounding approach. Following the recent trends in research and development as well as in industrial applications, TE has been working since 2010 towards the application of the statistical sensitivity and uncertainty analysis methods to the multi-physical modelling and licensing safety analyses. In this paper, the TE multi-physical modelling and safety analyses capability is first described, followed by the proposed TE best estimate plus statistical uncertainty analysis method (BESUAM). The chosen statistical sensitivity and uncertainty analysis methods (non-parametric order statistic method or bootstrap) and tool (DAKOTA) are then presented, followed by some preliminary results of their applications to FRAPCON/FRAPTRAN simulation of OECD RIA fuel rod codes benchmark and RELAP5/MOD3.3 simulation of THTF tests. (authors)

  20. Impact of the Global Food Safety Initiative on Food Safety Worldwide: Statistical Analysis of a Survey of International Food Processors.

    Science.gov (United States)

    Crandall, Philip G; Mauromoustakos, Andy; O'Bryan, Corliss A; Thompson, Kevin C; Yiannas, Frank; Bridges, Kerry; Francois, Catherine

    2017-10-01

    In 2000, the Consumer Goods Forum established the Global Food Safety Initiative (GFSI) to increase the safety of the world's food supply and to harmonize food safety regulations worldwide. In 2013, a university research team in conjunction with Diversey Consulting (Sealed Air), the Consumer Goods Forum, and officers of GFSI solicited input from more than 15,000 GFSI-certified food producers worldwide to determine whether GFSI certification had lived up to these expectations. A total of 828 usable questionnaires were analyzed, representing about 2,300 food manufacturing facilities and food suppliers in 21 countries, mainly across Western Europe, Australia, New Zealand, and North America. Nearly 90% of these certified suppliers perceived GFSI as being beneficial for addressing their food safety concerns, and respondents were eight times more likely to repeat the certification process knowing what it entailed. Nearly three-quarters (74%) of these food manufacturers would choose to go through the certification process again even if certification were not required by one of their current retail customers. Important drivers for becoming GFSI certified included continuing to do business with an existing customer, starting to do business with new customer, reducing the number of third-party food safety audits, and continuing improvement of their food safety program. Although 50% or fewer respondents stated that they saw actual increases in sales, customers, suppliers, or employees, significantly more companies agreed than disagreed that there was an increase in these key performance indicators in the year following GFSI certification. A majority of respondents (81%) agreed that there was a substantial investment in staff time since certification, and 50% agreed there was a significant capital investment. This survey is the largest and most representative of global food manufacturers conducted to date.

  1. Time series evaluation of landscape dynamics using annual Landsat imagery and spatial statistical modeling: Evidence from the Phoenix metropolitan region

    Science.gov (United States)

    Fan, Chao; Myint, Soe W.; Rey, Sergio J.; Li, Wenwen

    2017-06-01

    Urbanization is a natural and social process involving simultaneous changes to the Earth's land systems, energy flow, demographics, and the economy. Understanding the spatiotemporal pattern of urbanization is increasingly important for policy formulation, decision making, and natural resource management. A combination of satellite remote sensing and patch-based models has been widely adopted to characterize landscape changes at various spatial and temporal scales. Nevertheless, the validity of this type of framework in identifying long-term changes, especially subtle or gradual land modifications is seriously challenged. In this paper, we integrate annual image time series, continuous spatial indices, and non-parametric trend analysis into a spatiotemporal study of landscape dynamics over the Phoenix metropolitan area from 1991 to 2010. We harness local indicators of spatial dependence and modified Mann-Kendall test to describe the monotonic trends in the quantity and spatial arrangement of two important land use land cover types: vegetation and built-up areas. Results suggest that declines in vegetation and increases in built-up areas are the two prevalent types of changes across the region. Vegetation increases mostly occur at the outskirts where new residential areas are developed from natural desert. A sizable proportion of vegetation declines and built-up increases are seen in the central and southeast part. Extensive land conversion from agricultural fields into urban land use is one important driver of vegetation declines. The xeriscaping practice also contributes to part of vegetation loss and an increasingly heterogeneous landscape. The quantitative framework proposed in this study provides a pathway to effective landscape mapping and change monitoring from a spatial statistical perspective.

  2. 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...

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

    International Nuclear Information System (INIS)

    2008-01-01

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

  4. 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.

  5. 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

  6. 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

  7. 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)

  8. Are P values and statistical assessments in poster abstracts presented at annual meetings of Taiwan Society of Anesthesiologists relative to the characteristics of hospitals?

    Science.gov (United States)

    Lee, Fu-Jung; Wu, Chih-Cheng; Peng, Shih-Yen; Fan, Kuo-Tung

    2007-09-01

    Many anesthesiologists in medical centers (MC) or in anesthesiologist-training hospitals (ATH) are accustomed to present their research data in the form of poster abstracts at the annual meetings of Taiwan Society of Anesthesiologists (TSA) to represent their academic gainings in a designated period of time. However, an orphaned P value without mentioning the related specified statistical test has frequently been found in these articles. The difference in presentation of statistical test after P value between MC/ATH and non-MC/non-ATH in recent three TSA consecutive annual meetings was explored in this article. We collected the proceedings handbooks of TSA annual meetings in a period spanning 3 yrs (2003 to 2005) and analyzed the hospital characteristic of first institute-byliner in the poster abstract. Data were analyzed with Fisher's exact test and statistical significance was assumed if P poster abstracts with byliners of 20 hospitals. Only 2 of the 20 hospitals were accredited as non-ATH and 4 as non-MC. There were 64 (63%) abstracts without specified statistical test after P value and no significant difference was found among each category. (P = 0.47 in ATH vs. non-ATH and P = 0.07 in MC vs. non-MC). The basic concept of P value with specified statistical test was not applicable comprehensively in poster abstracts of the annual conferences. Based on our wishful intention, we suggest that the anesthesia administrators and senior anesthesiologists at ATH or MC, and the members of the committee responsible for running academic affairs in TSA, should pay attention to this prodigy and work together to improve our basic statistics in poster presentation.

  9. 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

  10. 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)

  11. 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.

  12. 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...

  13. 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

  14. 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

  15. 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.

  16. 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

  17. 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.

  18. 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

  19. 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

  20. 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).

  1. Timing and Statistics of Autumn and Spring Annual Snow Cover for the Northern Hemisphere, 1972 to 2000

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The National Snow and Ice Data Center hosts a time-series data set comprising annual snow cover data for the Northern Hemisphere (covering land primarily over 45...

  2. Non-clinical models: validation, study design and statistical consideration in safety pharmacology.

    Science.gov (United States)

    Pugsley, M K; Towart, R; Authier, S; Gallacher, D J; Curtis, M J

    2010-01-01

    The current issue of the Journal of Pharmacological and Toxicological Methods (JPTM) focuses exclusively on safety pharmacology methods. This is the 7th year the Journal has published on this topic. Methods and models that specifically relate to methods relating to the assessment of the safety profile of a new chemical entity (NCE) prior to first in human (FIH) studies are described. Since the Journal started publishing on this topic there has been a major effort by safety pharmacologists, toxicologists and regulatory scientists within Industry (both large and small Pharma as well as Biotechnology companies) and also from Contract Research Organizations (CRO) to publish the surgical details of the non-clinical methods utilized but also provide important details related to standard and non-standard (or integrated) study models and designs. These details from core battery and secondary (or ancillary) drug safety assessment methods used in drug development programs have been the focus of these special issues and have been an attempt to provide validation of methods. Similarly, the safety pharmacology issues of the Journal provide the most relevant forum for scientists to present novel and modified methods with direct applicability to determination of drug safety-directly to the safety pharmacology scientific community. The content of the manuscripts in this issue includes the introduction of additional important surgical methods, novel data capture and data analysis methods, improved study design and effects of positive control compounds with known activity in the model. Copyright 2010 Elsevier Inc. All rights reserved.

  3. 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.

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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

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

    International Nuclear Information System (INIS)

    2000-08-01

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

  10. 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.

  11. 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

  12. 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.)

  13. 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

  14. 17 CFR 240.17g-3 - Annual financial reports to be furnished by nationally recognized statistical rating organizations.

    Science.gov (United States)

    2010-04-01

    ... financial statements of the nationally recognized statistical rating organization or audited consolidated financial statements of its parent if the nationally recognized statistical rating organization is a...) of this section are consolidated financial statements of the parent of the nationally recognized...

  15. Perspectives on the application of order-statistics in best-estimate plus uncertainty nuclear safety analysis

    International Nuclear Information System (INIS)

    Martin, Robert P.; Nutt, William T.

    2011-01-01

    Research highlights: → Historical recitation on application of order-statistics models to nuclear power plant thermal-hydraulics safety analysis. → Interpretation of regulatory language regarding 10 CFR 50.46 reference to a 'high level of probability'. → Derivation and explanation of order-statistics-based evaluation methodologies considering multi-variate acceptance criteria. → Summary of order-statistics models and recommendations to the nuclear power plant thermal-hydraulics safety analysis community. - Abstract: The application of order-statistics in best-estimate plus uncertainty nuclear safety analysis has received a considerable amount of attention from methodology practitioners, regulators, and academia. At the root of the debate are two questions: (1) what is an appropriate quantitative interpretation of 'high level of probability' in regulatory language appearing in the LOCA rule, 10 CFR 50.46 and (2) how best to mathematically characterize the multi-variate case. An original derivation is offered to provide a quantitative basis for 'high level of probability.' At root of the second question is whether one should recognize a probability statement based on the tolerance region method of Wald and Guba, et al., for multi-variate problems, one explicitly based on the regulatory limits, best articulated in the Wallis-Nutt 'Testing Method', or something else entirely. This paper reviews the origins of the different positions, key assumptions, limitations, and relationship to addressing acceptance criteria. It presents a mathematical interpretation of the regulatory language, including a complete derivation of uni-variate order-statistics (as credited in AREVA's Realistic Large Break LOCA methodology) and extension to multi-variate situations. Lastly, it provides recommendations for LOCA applications, endorsing the 'Testing Method' and addressing acceptance methods allowing for limited sample failures.

  16. 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

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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

  2. 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.

  3. Estimating annual high-flow statistics and monthly and seasonal low-flow statistics for ungaged sites on streams in Alaska and conterminous basins in Canada

    Science.gov (United States)

    Wiley, Jeffrey B.; Curran, Janet H.

    2003-01-01

    Methods for estimating daily mean flow-duration statistics for seven regions in Alaska and low-flow frequencies for one region, southeastern Alaska, were developed from daily mean discharges for streamflow-gaging stations in Alaska and conterminous basins in Canada. The 15-, 10-, 9-, 8-, 7-, 6-, 5-, 4-, 3-, 2-, and 1-percent duration flows were computed for the October-through-September water year for 222 stations in Alaska and conterminous basins in Canada. The 98-, 95-, 90-, 85-, 80-, 70-, 60-, and 50-percent duration flows were computed for the individual months of July, August, and September for 226 stations in Alaska and conterminous basins in Canada. The 98-, 95-, 90-, 85-, 80-, 70-, 60-, and 50-percent duration flows were computed for the season July-through-September for 65 stations in southeastern Alaska. The 7-day, 10-year and 7-day, 2-year low-flow frequencies for the season July-through-September were computed for 65 stations for most of southeastern Alaska. Low-flow analyses were limited to particular months or seasons in order to omit winter low flows, when ice effects reduce the quality of the records and validity of statistical assumptions. Regression equations for estimating the selected high-flow and low-flow statistics for the selected months and seasons for ungaged sites were developed from an ordinary-least-squares regression model using basin characteristics as independent variables. Drainage area and precipitation were significant explanatory variables for high flows, and drainage area, precipitation, mean basin elevation, and area of glaciers were significant explanatory variables for low flows. The estimating equations can be used at ungaged sites in Alaska and conterminous basins in Canada where streamflow regulation, streamflow diversion, urbanization, and natural damming and releasing of water do not affect the streamflow data for the given month or season. Standard errors of estimate ranged from 15 to 56 percent for high-duration flow

  4. 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.

  5. 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)

  6. 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

  7. 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)

  8. 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)

  9. 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.

  10. Statistical evaluation of information reported to ISI and ISKO systems from a safety point of view

    International Nuclear Information System (INIS)

    Alonso Pallares, C.

    1993-01-01

    This paper describes he event percentages made by the main systems or equipment groups being the cause of incidents or directly linked to the incident. Command and protection systems, first-circuit equipment (BPC, VPC, volume compensator) safety systems, reactor installation and electrical input systems are analyzed. More over the main causes of notifies events are stressed and those where operation experience obtained in WWER-type nuclear power plants shows that and important part of incidents related to safety are due to personnel errors

  11. 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

  12. 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

  13. 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

  14. 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...

  15. 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...

  16. 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

  17. 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

  18. 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...

  19. 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

  20. 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.

  1. 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

  2. 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.

  3. 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

  4. 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)

  5. 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.)

  6. 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

  7. 1997 statistical yearbook

    International Nuclear Information System (INIS)

    1998-01-01

    The international office of energy information and studies (Enerdata), has published the second edition of its 1997 statistical yearbook which includes consolidated 1996 data with respect to the previous version from June 1997. The CD-Rom comprises the annual worldwide petroleum, natural gas, coal and electricity statistics from 1991 to 1996 with information about production, external trade, consumption, market shares, sectoral distribution of consumption and energy balance sheets. The world is divided into 12 zones (52 countries available). It contains also energy indicators: production and consumption tendencies, supply and production structures, safety of supplies, energy efficiency, and CO 2 emissions. (J.S.)

  8. 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

  9. 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)

  10. 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

  11. Uncertainty analysis of reactor safety systems with statistically correlated failure data

    International Nuclear Information System (INIS)

    Dezfuli, H.; Modarres, M.

    1985-01-01

    The probability of occurrence of the top event of a fault tree is estimated from failure probability of components that constitute the fault tree. Component failure probabilities are subject to statistical uncertainties. In addition, there are cases where the failure data are statistically correlated. Most fault tree evaluations have so far been based on uncorrelated component failure data. The subject of this paper is the description of a method of assessing the probability intervals for the top event failure probability of fault trees when component failure data are statistically correlated. To estimate the mean and variance of the top event, a second-order system moment method is presented through Taylor series expansion, which provides an alternative to the normally used Monte-Carlo method. For cases where component failure probabilities are statistically correlated, the Taylor expansion terms are treated properly. A moment matching technique is used to obtain the probability distribution function of the top event through fitting a Johnson Ssub(B) distribution. The computer program (CORRELATE) was developed to perform the calculations necessary for the implementation of the method developed. The CORRELATE code is very efficient and consumes minimal computer time. This is primarily because it does not employ the time-consuming Monte-Carlo method. (author)

  12. 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)

  13. 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.

  14. 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)

  15. 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)

  16. 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.

  17. Nuclear Level Densities for Modeling Nuclear Reactions: An Efficient Approach Using Statistical Spectroscopy: Annual Scientific Report July 2004

    International Nuclear Information System (INIS)

    Calvin W. Johnson

    2004-01-01

    The general goal of the project is to develop and implement computer codes and input files to compute nuclear densities of state. Such densities are important input into calculations of statistical neutron capture, and are difficult to access experimentally. In particular, we will focus on calculating densities for nuclides in the mass range A ?????? 50 - 100. We use statistical spectroscopy, a moments method based upon a microscopic framework, the interacting shell model. In this report we present our progress for the past year

  18. 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.)

  19. 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.

  20. 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.)

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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.

  10. 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)

  11. 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.

  12. 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

  13. 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.

  14. 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.

  15. 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

  16. Scientific Opinion on Statistical considerations for the safety evaluation of GMOs

    DEFF Research Database (Denmark)

    Sørensen, Ilona Kryspin

    in the experimental design of field trials, such as the inclusion of commercial varieties, in order to ensure sufficient statistical power and reliable estimation of natural variability. A graphical representation is proposed to allow the comparison of the GMO, its conventional counterpart and the commercial...... such estimates are unavailable may they be estimated from databases or literature. Estimated natural variability should be used to specify equivalence limits to test the difference between the GMO and the commercial varieties. Adjustments to these equivalence limits allow a simple graphical representation so...... in this opinion may be used, in certain cases, for the evaluation of GMOs other than plants....

  17. Statistics of past errors as a source of safety factors for current models

    International Nuclear Information System (INIS)

    Shlyakhter, A.I.

    1994-01-01

    Results of a comparative analysis of actual vs. estimated uncertainty in several data sets derived from natural and social sciences are presented. Data sets include: (i) time trends in the sequential measurements of the same physical quantity; (ii) environmental measurements of uranium in soil, (iii) national population projections; (iv) projections for the United States' energy sector. Probabilities of large deviations from the true values are parametrized by an exponential distribution with the slope determined by the data. One can hedge against unsuspected uncertainties by inflating reported uncertainty range by a default safety factor determined from the relevant historical data sets. This emperical approach can be used in the uncertainty analysis of the low probability/high consequence events, such as risk of global warming

  18. 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.)

  19. CMS Statistics

    Data.gov (United States)

    U.S. Department of Health & Human Services — The CMS Center for Strategic Planning produces an annual CMS Statistics reference booklet that provides a quick reference for summary information about health...

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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)

  5. 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)

  6. 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)

  7. Nonequilibrium statistical physics of small systems: fluctuation relations and beyond (annual reviews of nonlinear dynamics and complexity (vch))

    CERN Document Server

    2013-01-01

    This book offers a comprehensive picture of nonequilibrium phenomena in nanoscale systems. Written by internationally recognized experts in the field, this book strikes a balance between theory and experiment, and includes in-depth introductions to nonequilibrium fluctuation relations, nonlinear dynamics and transport, single molecule experiments, and molecular diffusion in nanopores. The authors explore the application of these concepts to nano- and biosystems by cross-linking key methods and ideas from nonequilibrium statistical physics, thermodynamics, stochastic theory, and dynamical s

  8. 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

  9. 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

  10. State Transportation Statistics 2014

    Science.gov (United States)

    2014-12-15

    The Bureau of Transportation Statistics (BTS) presents State Transportation Statistics 2014, a statistical profile of transportation in the 50 states and the District of Columbia. This is the 12th annual edition of State Transportation Statistics, a ...

  11. 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.)

  12. Safety bey statistics? A critical view on statistical methods applied in health physics; Sicherheit durch Statistik? Ein kritischer Blick auf die Anwendung statistischer Methoden im Strahlenschutz

    Energy Technology Data Exchange (ETDEWEB)

    Kraut, W. [Duale Hochschule Baden-Wuerttemberg (DHBW), Karlsruhe (Germany). Studiengang Sicherheitswesen

    2016-07-01

    The only proper way to describe uncertainties in health physics is by statistical means. But statistics never can replace Your personal evaluation of effect, nor can statistics transmute randomness into certainty like an ''uncertainty laundry''. The paper discusses these problems in routine practical work.

  13. 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

  14. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Panka, Istvan; Hegyi, Gyoergy; Maraczy, Csaba; Temesvari, Emese [Hungarian Academy of Sciences, Budapest (Hungary). Reactor Analysis Dept.

    2017-11-15

    The best-estimate KARATE code system has been widely used for core design calculations and simulations of slow transients of VVER reactors. Recently there has been an increasing need for assessing the uncertainties of such calculations by propagating the basic input uncertainties of the models through the full calculation chain. In order to determine the uncertainties of quantities of interest during the burnup, the statistical version of the KARATE code system has been elaborated. In the first part of the paper, the main features of the new code system are discussed. The applied statistical method is based on Monte-Carlo sampling of the considered input data taking into account mainly the covariance matrices of the cross sections and/or the technological uncertainties. In the second part of the paper, only the uncertainties of cross sections are considered and an equilibrium cycle related to a VVER-440 type reactor is investigated. The burnup dependence of the uncertainties of some safety related parameters (e.g. critical boron concentration, rod worth, feedback coefficients, assembly-wise radial power and burnup distribution) are discussed and compared to the recently used limits.

  15. 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)

  16. Modelling spatial relationship between climatic conditions and annual parasite incidence of malaria in southern part of Sistan&Balouchistan Province of Iran using spatial statistic models

    Directory of Open Access Journals (Sweden)

    Mansour Halimi

    2014-02-01

    Full Text Available Objective: To model spatial relationship between climatic conditions and annual parasite incidence (API of malaria in southern part of Sistan&Balouchistan Province of Iran using spatial statistic models . Methods: A geographical weighted regression model was applied for predicting API by 3 climatic factors in order to model the spatial API of malaria in Sistan&Baluchistan Province of Iran. Results: The results indicated that most important climatic factor for explaining API in Sistan&Baluchistan was annual rainfall being of more importance in southern part of study area such as Chabahar, and Nikshar. The temperature and relative humidity are of the second and third priority respectively. The importance of these two climatic factors is higher in northern part of the studied region. The spatial autocorrelation (Moran ’s I for standard residual of applied geographical weighted regression model is -0.022 which indicated no spatial patterns. Conclusions: This model explained only 0.51 of API spatial variation (R2=0.51. Thus, the nonclimatic factors such as socioeconomic, lifestyle and the neighborhood position of this province with Afghanistan, and Pakistan also should be considered in epidemiological survey of malaria in Sistan&Baluchistan.

  17. 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.

  18. 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.

  19. 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.

  20. Youth Sports Safety Statistics

    Science.gov (United States)

    ... supplements, steroids, changed eating, exercising, other muscle enhancing tactics, etc. was more than twice as high among boys who participated in sports vs. nonparticipants. 36  The occurrence of energy drink- ...

  1. 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.)

  2. 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.)

  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

    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.)

  4. 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

  5. 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

  6. 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

  7. 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.)

  8. 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)

  9. 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...

  10. 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...

  11. 96. Annual report: 1985

    International Nuclear Information System (INIS)

    1986-01-01

    The annual report of the Chamber of Mines of South Africa covers various aspects of mining in South Africa during 1985. The report deals with coal, diamonds, gold, platinum and uranium. It also covers research, safety, industrial relations, taxation and the South African economy. Statistical tables on information concerning coal, gold, silver and uranium are also given. Long-term economic views strongly favour nuclear-generated electricity in most parts of the world and thus the demand for uranium can be expected to increase with rising energy needs. During 1985 members of the Nuclear Fuels Corporation of South Africa (Nufcor) produced 5541 metric ton U 3 O 8 . Statistics are given on the production of Uranium Oxide U 3 O 8 at the different South African mines. A quarterley analysis of working results during the year 1985 are given

  12. 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.

  13. 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.

  14. 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)

  15. 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.

  16. 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.

  17. 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.

  18. The SRTR/OPTN Annual Data Report

    Science.gov (United States)

    ... Annual Data Report The SRTR/OPTN Annual Data Report Statistics on donation and transplantation in the United ... US in 2015. The SRTR/OPTN Annual Data Report SRTR/OPTN Annual Data Report Learn more from ...

  19. 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)

  20. 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)