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Sample records for safety research division

  1. Health and Safety Research Division progress report, October 1, 1982-June 30, 1984

    International Nuclear Information System (INIS)

    Kaye, S.V.

    1984-08-01

    The work accomplished by the Health and Safety Research Division, Oak Ridge National Laboratory is summarized. Research, assessments and technical measurements done by the division between October 1982 and June 1984 are summarized. Separate analytics were written for each chapter

  2. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  3. Systems Safety and Engineering Division

    Data.gov (United States)

    Federal Laboratory Consortium — Volpe's Systems Safety and Engineering Division conducts engineering, research, and analysis to improve transportation safety, capacity, and resiliency. We provide...

  4. Health and Safety Research Division progress report for period ending April 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Kaye, S.V.

    1978-08-01

    The research goal of the Health and Safety Research Division is to conduct basic and applied research that contributes new scientific knowledge with emphasis in biophysical areas that lead to a better understanding of how alternative energy-related technologies affect man. Included in the basic research are fundamental processes that are important to understand formation, mobility, toxicity, detection, and characterization of pollutants. The applied research includes the integration of data from basic and applied studies through development of concepts and methodologies that can be used for energy-related assessments with primary focus on the health and safety of man. The division has no responsibilities for on-site health and safety.

  5. Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993

    International Nuclear Information System (INIS)

    Berven, B.A.

    1993-09-01

    This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration

  6. Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Berven, B.A.

    1993-09-01

    This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration.

  7. Health and Safety Research Division progress report for the period April 1, 1990--September 30, 1991

    Energy Technology Data Exchange (ETDEWEB)

    Kaye, S.V.

    1992-03-01

    This is a brief progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology including Measurement Applications and Development, Pollutant Assessments, Measurement Systems Research, Dosimetry Applications Research, Metabolism and Dosimetry Research and Nuclear Medicine. Biological and Radiation Physics including Atomic, Molecular, and High Voltage Physics, Physics of Solids and Macromolecules, Liquid and Submicron Physics, Analytic Dosimetry and Surface Physics and Health Effects. Chemical Physics including Molecular Physics, Photophysics and Advanced Monitoring Development. Biomedical and Environmental Information Analysis including Human Genome and Toxicology, Chemical Hazard Evaluation and Communication, Environmental Regulations and Remediation and Information Management Technology. Risk Analysis including Hazardous Waste.

  8. Health and Safety Research Division progress report, October 1, 1988--March 31, 1990

    International Nuclear Information System (INIS)

    1990-09-01

    The Health and Safety Research Division (HASRD) of the Oak Ridge National Laboratory (ORNL) continues to maintain an outstanding program of basic and applied research displaying a high level of creativity and achievement as documented by awards, publications, professional service, and successful completion of variety of projects. Our focus is on human health and the scientific basis for measurement and assessment of health-related impacts of energy technologies. It is our custom to publish a division progress report every 18 months that summarizes our programmatic progress and other measures of achievement over the reporting period. Since it is not feasible to summarize in detail all of our work over the period covered by this report (October 1, 1988, to March 30, 1990), we intend this document to point the way to the expensive open literature that documents our findings. During the reporting period the Division continued to maintain strong programs in its traditional areas of R ampersand D, but also achieved noteworthy progress in other areas. Much of the Division's work on site characterization, development of new field instruments, compilation of data bases, and methodology development fits into this initiative. Other new work in tunneling microscopy in support of DOE's Human Genome Program and the comprehensive R ampersand D work related to surface-enhanced Raman spectroscopy have attained new and exciting results. These examples of our progress and numerous other activities are highlighted in this report

  9. Health and Safety Research Division progress report, October 1, 1988--March 31, 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-01

    The Health and Safety Research Division (HASRD) of the Oak Ridge National Laboratory (ORNL) continues to maintain an outstanding program of basic and applied research displaying a high level of creativity and achievement as documented by awards, publications, professional service, and successful completion of variety of projects. Our focus is on human health and the scientific basis for measurement and assessment of health-related impacts of energy technologies. It is our custom to publish a division progress report every 18 months that summarizes our programmatic progress and other measures of achievement over the reporting period. Since it is not feasible to summarize in detail all of our work over the period covered by this report (October 1, 1988, to March 30, 1990), we intend this document to point the way to the expensive open literature that documents our findings. During the reporting period the Division continued to maintain strong programs in its traditional areas of R D, but also achieved noteworthy progress in other areas. Much of the Division's work on site characterization, development of new field instruments, compilation of data bases, and methodology development fits into this initiative. Other new work in tunneling microscopy in support of DOE's Human Genome Program and the comprehensive R D work related to surface-enhanced Raman spectroscopy have attained new and exciting results. These examples of our progress and numerous other activities are highlighted in this report.

  10. Health and Safety Research Division progress report for the period April 1, 1987--September 30, 1988

    International Nuclear Information System (INIS)

    Kaye, S.V.

    1989-03-01

    The mission of the Health and Safety Research Division (HASRD) is to provide a sound scientific basis for the measurement and assessment of human health impacts of radiological and chemical substances. Our approach to fulfilling this mission is to conduct a broad program of experimental, theoretical, and field research based on a strong foundation of fundamental physical studies that blend into well-established programs in life sciences. Topics include biomedical screening techniques, biological and chemical sensors, risk assessment, health hazards, dosimetry, nuclear medicine, environmental pollution monitoring, electron-molecule interactions, interphase physics, surface physics, data base management, environmental mutagens, carcinogens, and tetratogens

  11. Health and Safety Research Division progress report for the period April 1, 1987--September 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Kaye, S.V.

    1989-03-01

    The mission of the Health and Safety Research Division (HASRD) is to provide a sound scientific basis for the measurement and assessment of human health impacts of radiological and chemical substances. Our approach to fulfilling this mission is to conduct a broad program of experimental, theoretical, and field research based on a strong foundation of fundamental physical studies that blend into well-established programs in life sciences. Topics include biomedical screening techniques, biological and chemical sensors, risk assessment, health hazards, dosimetry, nuclear medicine, environmental pollution monitoring, electron-molecule interactions, interphase physics, surface physics, data base management, environmental mutagens, carcinogens, and tetratogens.

  12. Health, Safety, and Environment Division

    Energy Technology Data Exchange (ETDEWEB)

    Wade, C [comp.

    1992-01-01

    The primary responsibility of the Health, Safety, and Environmental (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. Meeting these responsibilities requires expertise in many disciplines, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science and engineering, analytical chemistry, epidemiology, and waste management. New and challenging health, safety, and environmental problems occasionally arise from the diverse research and development work of the Laboratory, and 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. The results of these programs help develop better practices in occupational health and safety, radiation protection, and environmental science.

  13. Student research activities in the Technology Assessments Section of the Health and Safety Research Division, Summer 1980

    Energy Technology Data Exchange (ETDEWEB)

    Chester, R.O.; Roberts, D.A.

    1981-08-01

    Reports summarizing activities of students assigned to the Technology Assessments Section of the Health and Safety Research Division for the summer 1980 are presented. Unless indicated otherwise, each report was written by the student whose work is being described. For each student, the student's supervisor, the name of the program under which the student was brought to ORNL, the academic level of the student, and the name of the ORNL project to which the student was assigned are tabulated. The reports are presented in alphabetical order of the students' last names.

  14. Student research activities in the Technology Assessments Section of the Health and Safety Research Division, Summer 1980

    International Nuclear Information System (INIS)

    Chester, R.O.; Roberts, D.A.

    1981-08-01

    Reports summarizing activities of students assigned to the Technology Assessments Section of the Health and Safety Research Division for the summer 1980 are presented. Unless indicated otherwise, each report was written by the student whose work is being described. For each student, the student's supervisor, the name of the program under which the student was brought to ORNL, the academic level of the student, and the name of the ORNL project to which the student was assigned are tabulated. The reports are presented in alphabetical order of the students' last names

  15. Occupational health and environment research 1983: Health, Safety, and Environment Division. Progress report

    International Nuclear Information System (INIS)

    Voelz, G.L.

    1985-05-01

    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 workers, the public, and the environment. Evaluation of respiratory protective equipment included the XM-30 and M17A1 military masks, use of MAG-1 spectacles in respirators, and eight self-contained units. The latter units were used in an evaluation of test procedures used for Bureau of Mines approval of breathing apparatuses. Analyses of air samples from field studies of a modified in situ oil shale retorting facility were performed for total cyclohexane extractables and selected polynuclear aromatic hydrocarbons. Aerosols generation and characterization of effluents from oil shale processing were continued as part of an inhalation toxicology study. Additional data on plutonium excretion in urine are presented and point up problems in using the Langham equation to predict plutonium deposition in the body from long-term excretion data. Environmental surveillance at Los Alamos during 1983 showed the highest estimated radiation dose from Laboratory operations to be about 26% of the natural background radiation dose. Several studies on radionuclides and their transport in the Los Alamos environment are described. The chemical quality of surface and ground water near the geothermal hot dry rock facility is described. Short- and long-term consequences to man from releases of radionuclides into the environment can be simulated by the BIOTRAN computer model, which is discussed brirfly

  16. Occupational health and environment research 1984: Health, Safety, and environmental Division. Progress report

    International Nuclear Information System (INIS)

    Voelz, G.L.

    1986-05-01

    The primary responsibility of the Health, Safety, and Environment (HSE) Division is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. Two supplied-air suits tested for their functional protection were considered to be unacceptable because of low fit factors. Respiratory protective equipment testing for the uS Air Force, Navy, and Army was performed during 1984. The laser aerosol spectrometer (LAS-X) has been shown to operate successfully for measuring and sizing aerosols used for quality assurance testing of high-efficiency particulate air filters used at DOE facilities. Radioanalyses for 239 Pu and 241 Am are presented for the complete skeletal parts of two persons. Air samples from work areas in a coal gasification plant in Yugoslavia show minimal concentration of organic vapors, amines, polynuclear aromatic hydrocarbons, and phenols. Aerosol characteristics of oil shale vapors and manmade vitreous fibers used in ongoing inhalation toxicology studies are presented. Epidemiologic studies of smoking patterns among Los Alamos employees reveal 24.3% smokers compared with the US rate of 32.5%. Environmental surveillance at Los Alamos during 1984 showed the highest estimated radiation dose to an individual at or outside the Laboratory boundary to be about 25% of the natural background radiation dose. Surveillance studies on water and sediment transport of radionuclides, depleted uranium, and silver are described. Bibliographic review of the rooting depth of native plants indicates that even many grass species will root to depths greater than the earth overburden depths to cover low-level radioactive waste sites

  17. Ontario Hydro Research Division, 1980

    International Nuclear Information System (INIS)

    The work of the Research Division of Ontario Hydro provides technical and scientific support for the engineering and operation of a power system that includes hydraulic, fossil-fired, and nuclear generation. It also relates to the transmission and distribution of electricity and to the need to help customers use electricity with safety and economy. Among the examples of projects given are qualification of CANDU heat transport system components, pressure tube replacement, steam generator integrity, testing for earthquake resistance, and radioactive waste disposal

  18. Health and Safety Research Division: Progress report, October 1, 1985-March 31, 1987

    International Nuclear Information System (INIS)

    Walsh, P.J.

    1987-09-01

    This report summarizes the progress in our programs for the period October 1, 1985, through March 31, 1987. The division's presentations and publications represented important contributions on the forefronts of many fields. Eleven invention disclosures were filed, two patent applications submitted, and one patent issued. The company's transfers new technologies to the private sector more efficiently than in the past. The division's responsibilities to DOE under the Uranium Mill Tailings Remedial Action (UMTRA) program includes inclusion recommendations for 3100 properties. The nuclear medicine program developed new radiopharmaceuticals and radionuclide generators through clinical trials with some of our medical cooperatives. Two major collaborative indoor air quality studies and a large epidemiological study of drinking water quality and human health were completed. ORNL's first scanning tunneling microscope (STM) has achieved single atom resolution and has produced some of the world's best images of single atoms on the surface of a silicon crystal. The Biological and Radiation Physics Section, designed and constructed a soft x-ray spectrometer which has exhibited a measuring efficiency that is 10,000 times higher than other equipment. 1164 refs

  19. Health and Safety Research Division: Progress report, October 1, 1985-March 31, 1987

    Energy Technology Data Exchange (ETDEWEB)

    Walsh, P.J.

    1987-09-01

    This report summarizes the progress in our programs for the period October 1, 1985, through March 31, 1987. The division's presentations and publications represented important contributions on the forefronts of many fields. Eleven invention disclosures were filed, two patent applications submitted, and one patent issued. The company's transfers new technologies to the private sector more efficiently than in the past. The division's responsibilities to DOE under the Uranium Mill Tailings Remedial Action (UMTRA) program includes inclusion recommendations for 3100 properties. The nuclear medicine program developed new radiopharmaceuticals and radionuclide generators through clinical trials with some of our medical cooperatives. Two major collaborative indoor air quality studies and a large epidemiological study of drinking water quality and human health were completed. ORNL's first scanning tunneling microscope (STM) has achieved single atom resolution and has produced some of the world's best images of single atoms on the surface of a silicon crystal. The Biological and Radiation Physics Section, designed and constructed a soft x-ray spectrometer which has exhibited a measuring efficiency that is 10,000 times higher than other equipment. 1164 refs.

  20. Annual report of contract research for the Metallurgy and Materials Research Branch, Division of Reactor Safety Research, Fiscal Year 1977

    International Nuclear Information System (INIS)

    1978-05-01

    Research is reported in the areas of: fracture and structural mechanics; non-destructive testing; steam generator integrity and corrosion; pressure vessel surveillance dosimetry and piping system analysis

  1. Health and Safety Research Division. Progress report, October 1, 1979-March 31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    Research progress for the period October 1, 1979 through March 31, 1981 is reported. Research conducted by the Office of Integrated Assessments and Policy Analysis, Health Studies Section, Technology Assessments Section, Biological and Radiation Physics Section, and Chemical Physics Section is summarized. (ACR)

  2. Health and Safety Research Division. Progress report, October 1, 1979-March 31, 1981

    International Nuclear Information System (INIS)

    1981-08-01

    Research progress for the period October 1, 1979 through March 31, 1981 is reported. Research conducted by the Office of Integrated Assessments and Policy Analysis, Health Studies Section, Technology Assessments Section, Biological and Radiation Physics Section, and Chemical Physics Section is summarized

  3. Health and Safety Research Division progress report, April 1, 1981-September 30, 1982

    International Nuclear Information System (INIS)

    1983-02-01

    Research progress for the reporting period is briefly summarized for the following sections: (1) health studies, (2) technology assessments, (3) biological and radiation physics, (4) chemical physics, (5) Office of Risk Analysis, and (6) health and environmental risk and analysis

  4. Health and Safety Research Division progress report, July 1, 1984-September 30, 1985

    International Nuclear Information System (INIS)

    1986-01-01

    This report summarizes progress made for the period July 1984 through September 1985. Sections describe research in health studies, dosimetry and biophysical transport, biological and radiation physics, chemical physics, and risk analysis

  5. Health and Safety Research Division progress report, July 1, 1984-September 30, 1985

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    This report summarizes progress made for the period July 1984 through September 1985. Sections describe research in health studies, dosimetry and biophysical transport, biological and radiation physics, chemical physics, and risk analysis. (ACR)

  6. Energy Research and Development Administration, Division of Safety, Standards, and Compliance respirator manual

    International Nuclear Information System (INIS)

    Douglas, D.D.; Hack, A.L.; Held, B.J.; Revoir, W.H.

    1976-05-01

    The manual has been prepared to provide technical information for contractors of the Energy Research and Development Administration (ERDA) on the application of respiratory protective devices for protection against airborne contaminants, both radioactive and nonradioactive. The various elements of a respirator program including selection and maintenance of equipment and training of personnel are described to assist in establishing adequate programs

  7. Energy Research and Development Administration, Division of Safety, Standards, and Compliance respirator manual

    Energy Technology Data Exchange (ETDEWEB)

    Douglas, D.D.; Hack, A.L.; Held, B.J.; Revoir, W.H.

    1976-05-01

    The manual has been prepared to provide technical information for contractors of the Energy Research and Development Administration (ERDA) on the application of respiratory protective devices for protection against airborne contaminants, both radioactive and nonradioactive. The various elements of a respirator program including selection and maintenance of equipment and training of personnel are described to assist in establishing adequate programs.

  8. Health and Safety Research Division progress report, April 1, 1981-September 30, 1982

    Energy Technology Data Exchange (ETDEWEB)

    1983-02-01

    Research progress for the reporting period is briefly summarized for the following sections: (1) health studies, (2) technology assessments, (3) biological and radiation physics, (4) chemical physics, (5) Office of Risk Analysis, and (6) health and environmental risk and analysis. (ACR)

  9. Energy Technology Division research summary 2004

    International Nuclear Information System (INIS)

    Poeppel, R. B.; Shack, W. J.

    2004-01-01

    The Energy Technology (ET) Division provides materials and engineering technology support to a wide range of programs important to the US Department of Energy (DOE). The Division's capabilities are generally applied to technical issues associated with energy systems, biomedical engineering, transportation, and homeland security. Research related to the operational safety of commercial light water nuclear reactors (LWRs) for the US Nuclear Regulatory Commission (NRC) remains another significant area of interest for the Division. The pie chart below summarizes the ET sources of funding for FY 2004

  10. Progress report: 1996 Radiation Safety Systems Division

    International Nuclear Information System (INIS)

    Bhagwat, A.M.; Sharma, D.N.; Abani, M.C.; Mehta, S.K.

    1997-01-01

    The activities of Radiation Safety Systems Division include (i) development of specialised monitoring systems and radiation safety information network, (ii) radiation hazards control at the nuclear fuel cycle facilities, the radioisotope programmes at Bhabha Atomic Research Centre (BARC) and for the accelerators programme at BARC and Centre for Advanced Technology (CAT), Indore. The systems on which development and upgradation work was carried out during the year included aerial gamma spectrometer, automated environment monitor using railway network, radioisotope package monitor and air monitors for tritium and alpha active aerosols. Other R and D efforts at the division included assessment of risk for radiation exposures and evaluation of ICRP 60 recommendations in the Indian context, shielding evaluation and dosimetry for the new upcoming accelerator facilities and solid state nuclear track detector techniques for neutron measurements. The expertise of the divisional members was provided for 36 safety committees of BARC and Atomic Energy Regulatory Board (AERB). Twenty three publications were brought out during the year 1996. (author)

  11. Energy Technology Division research summary 2001

    International Nuclear Information System (INIS)

    2001-01-01

    The Energy Technology Division provides materials and engineering technology support to a wide range of programs important to the U.S. Department of Energy. As shown on the preceding page, the Division is organized into eight sections, four with concentrations in the materials area and four in engineering technology. Materials expertise includes fabrication, mechanical properties, corrosion, friction and lubrication, and irradiation effects. Our major engineering strengths are in heat and mass flow, sensors and instrumentation, nondestructive testing, transportation, and electromechanics and superconductivity applications. The Division Safety Coordinator, Environmental Compliance Officer, Quality Assurance Representative, Financial Administrator, and Communication Coordinator report directly to the Division Director. The Division Director is personally responsible for cultural diversity and is a member of the Laboratory-wide Cultural Diversity Advisory Committee. This Overview highlights some major ET research areas. Research related to the operational safety of commercial light water nuclear reactors (LWRs) for the U.S. Nuclear Regulatory Commission (NRC) remains a significant area of interest for the Division. We currently have programs on environmentally assisted cracking, steam generator integrity, and the integrity of high-burnup fuel during loss-of-coolant accidents. The bulk of the NRC research work is carried out by three ET sections: Corrosion and Mechanics of Materials; Irradiation Performance; and Sensors, Instrumentation, and Nondestructive Evaluation

  12. Energy Technology Division research summary - 1999.

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-31

    The Energy Technology Division provides materials and engineering technology support to a wide range of programs important to the US Department of Energy. As shown on the preceding page, the Division is organized into ten sections, five with concentrations in the materials area and five in engineering technology. Materials expertise includes fabrication, mechanical properties, corrosion, friction and lubrication, and irradiation effects. Our major engineering strengths are in heat and mass flow, sensors and instrumentation, nondestructive testing, transportation, and electromechanics and superconductivity applications. The Division Safety Coordinator, Environmental Compliance Officers, Quality Assurance Representative, Financial Administrator, and Communication Coordinator report directly to the Division Director. The Division Director is personally responsible for cultural diversity and is a member of the Laboratory-wide Cultural Diversity Advisory Committee. The Division's capabilities are generally applied to issues associated with energy production, transportation, utilization, or conservation, or with environmental issues linked to energy. As shown in the organization chart on the next page, the Division reports administratively to the Associate Laboratory Director (ALD) for Energy and Environmental Science and Technology (EEST) through the General Manager for Environmental and Industrial Technologies. While most of our programs are under the purview of the EEST ALD, we also have had programs funded under every one of the ALDs. Some of our research in superconductivity is funded through the Physical Research Program ALD. We also continue to work on a number of nuclear-energy-related programs under the ALD for Engineering Research. Detailed descriptions of our programs on a section-by-section basis are provided in the remainder of this book.

  13. HSE Nuclear Safety Research Program

    Energy Technology Data Exchange (ETDEWEB)

    Bagley, M.J. [Health and Safety Executive, Sheffield (United Kingdom)

    1995-12-31

    HSE funds two programmes of nuclear safety research: a programme of {approx} 2.2M of extramural research to support the Nuclear Safety Division`s regulatory activities and a programme of {approx} 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author).

  14. 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.

  15. 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

  16. 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

  17. Nuclear Power and Safety Division activity

    International Nuclear Information System (INIS)

    Pazdera, F.

    1991-01-01

    History of the Division is briefly described. Present research is centered on reliability analyses and thermal hydraulic analyses of transients and accidents. Some results of the safety analyses have been applied at nuclear power plants. A characterization is presented of computer codes for analyzing the behavior of fuel in normal and accident conditions. Research activities in the field of water chemistry and corrosion are oriented to the corrosion process at high temperatures and high pressures, and the related mass and radioactivity transfer; the effect of some chemical processes on primary coolant circuit materials; optimization of PWR filtration systems; and the development of the requisite monitoring instrumentation. A computerized operator support system has been developed, and at present it is tested at the Dukovany nuclear power plant. A program of nuclear fuel cycle strategy and economy has been worked out for nuclear fuel performance evaluation. Various options for better fuel exploitation, alternatives for advanced fuelling, and fuel cycle costs are assessed, and out-of-reactor fuel cycle options are compared. (M.D.). 7 refs., 32 refs

  18. Energy Technology Division research summary -- 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    Research funded primarily by the NRC is directed toward assessing the roles of cyclic fatigue, intergranular stress corrosion cracking, and irradiation-assisted stress corrosion cracking on failures in light water reactor (LWR) piping systems, pressure vessels, and various core components. In support of the fast reactor program, the Division has responsibility for fuel-performance modeling and irradiation testing. The Division has major responsibilities in several design areas of the proposed International Thermonuclear Experimental Reactor (ITER). The Division supports the DOE in ensuring safe shipment of nuclear materials by providing extensive review of the Safety Analysis Reports for Packaging (SARPs). Finally, in the nuclear area they are investigating the safe disposal of spent fuel and waste. In work funded by DOE`s Energy Efficiency and Renewable Energy, the high-temperature superconductivity program continues to be a major focal point for industrial interactions. Coatings and lubricants developed in the division`s Tribology Section are intended for use in transportation systems of the future. Continuous fiber ceramic composites are being developed for high-performance heat engines. Nondestructive testing techniques are being developed to evaluate fiber distribution and to detect flaws. A wide variety of coatings for corrosion protection of metal alloys are being studied. These can increase lifetimes significant in a wide variety of coal combustion and gasification environments.

  19. Energy Technology Division research summary 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The Energy Technology Division provides materials and engineering technology support to a wide range of programs important to the US Department of Energy. As shown on the preceding page, the Division is organized into ten sections, five with concentrations in the materials area and five in engineering technology. Materials expertise includes fabrication, mechanical properties, corrosion, friction and lubrication, and irradiation effects. Our major engineering strengths are in heat and mass flow, sensors and instrumentation, nondestructive testing, transportation, and electromechanics and superconductivity applications. The Division Safety Coordinator, Environmental Compliance Officers, Quality Assurance Representative, Financial Administrator, and Communication Coordinator report directly to the Division Director. The Division Director is personally responsible for cultural diversity and is a member of the Laboratory-wide Cultural Diversity Advisory Committee. The Division's capabilities are generally applied to issues associated with energy production, transportation, utilization or conservation, or with environmental issues linked to energy. As shown in the organization chart on the next page, the Division reports administratively to the Associate Laboratory Director (ALD) for Energy and Environmental Science and Technology (EEST) through the General Manager for Environmental and Industrial Technologies. While most of our programs are under the purview of the EEST ALD, we also have had programs funded under every one of the ALDs. Some of our research in superconductivity is funded through the Physical Research Program ALD. We also continue to work on a number of nuclear-energy-related programs under the ALD for Engineering Research. Detailed descriptions of our programs on a section-by-section basis are provided in the remainder of this book. This Overview highlights some major trends. Research related to the operational safety of commercial light water nuclear

  20. Energy Technology Division research summary 1997.

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-21

    The Energy Technology Division provides materials and engineering technology support to a wide range of programs important to the US Department of Energy. As shown on the preceding page, the Division is organized into ten sections, five with concentrations in the materials area and five in engineering technology. Materials expertise includes fabrication, mechanical properties, corrosion, friction and lubrication, and irradiation effects. Our major engineering strengths are in heat and mass flow, sensors and instrumentation, nondestructive testing, transportation, and electromechanics and superconductivity applications. The Division Safety Coordinator, Environmental Compliance Officers, Quality Assurance Representative, Financial Administrator, and Communication Coordinator report directly to the Division Director. The Division Director is personally responsible for cultural diversity and is a member of the Laboratory-wide Cultural Diversity Advisory Committee. The Division's capabilities are generally applied to issues associated with energy production, transportation, utilization or conservation, or with environmental issues linked to energy. As shown in the organization chart on the next page, the Division reports administratively to the Associate Laboratory Director (ALD) for Energy and Environmental Science and Technology (EEST) through the General Manager for Environmental and Industrial Technologies. While most of our programs are under the purview of the EEST ALD, we also have had programs funded under every one of the ALDs. Some of our research in superconductivity is funded through the Physical Research Program ALD. We also continue to work on a number of nuclear-energy-related programs under the ALD for Engineering Research. Detailed descriptions of our programs on a section-by-section basis are provided in the remainder of this book. This Overview highlights some major trends. Research related to the operational safety of commercial light water

  1. Energy Technology Division research summary -- 1994

    International Nuclear Information System (INIS)

    1994-09-01

    Research funded primarily by the NRC is directed toward assessing the roles of cyclic fatigue, intergranular stress corrosion cracking, and irradiation-assisted stress corrosion cracking on failures in light water reactor (LWR) piping systems, pressure vessels, and various core components. In support of the fast reactor program, the Division has responsibility for fuel-performance modeling and irradiation testing. The Division has major responsibilities in several design areas of the proposed International Thermonuclear Experimental Reactor (ITER). The Division supports the DOE in ensuring safe shipment of nuclear materials by providing extensive review of the Safety Analysis Reports for Packaging (SARPs). Finally, in the nuclear area they are investigating the safe disposal of spent fuel and waste. In work funded by DOE's Energy Efficiency and Renewable Energy, the high-temperature superconductivity program continues to be a major focal point for industrial interactions. Coatings and lubricants developed in the division's Tribology Section are intended for use in transportation systems of the future. Continuous fiber ceramic composites are being developed for high-performance heat engines. Nondestructive testing techniques are being developed to evaluate fiber distribution and to detect flaws. A wide variety of coatings for corrosion protection of metal alloys are being studied. These can increase lifetimes significant in a wide variety of coal combustion and gasification environments

  2. Safety and Health Division achievements during 40 years

    International Nuclear Information System (INIS)

    Noriah Mod Ali

    2012-01-01

    During her speech, presenter outlined several issues regarding on establishment of Safety and Health Division since 40 years. This division contain of 3 sub unit; Physical Safety Group, Medical Physic Group and Non-ionizing Radiation group (NIR). The objectives of this division to implement R and D activities and services regarding safety and radiological health also non-radiological to ensure public safety, environment and asset suit with obligations established by authorities, IAEA standards and regulations.(author)

  3. HSE Nuclear Safety Research Program

    International Nuclear Information System (INIS)

    Bagley, M.J.

    1995-01-01

    HSE funds two programmes of nuclear safety research: a programme of ∼ 2.2M of extramural research to support the Nuclear Safety Division's regulatory activities and a programme of ∼ 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author)

  4. Ecological Research Division, Marine Research Program

    Energy Technology Data Exchange (ETDEWEB)

    1980-05-01

    This report presents program summaries of the various projects sponsored during 1979 by the Marine Research Program of the Ecological Research Division. Program areas include the effects of petroleum hydrocarbons on the marine environment; a study of the baseline ecology of a proposed OTEC site near Puerto Rico; the environmental impact of offshore geothermal energy development; the movement of radionuclides through the marine environment; the environmental aspects of power plant cooling systems; and studies of the physical and biological oceangraphy of the continental shelves bordering the United States.

  5. Ecological Research Division, Marine Research Program

    International Nuclear Information System (INIS)

    1980-05-01

    This report presents program summaries of the various projects sponsored during 1979 by the Marine Research Program of the Ecological Research Division. Program areas include the effects of petroleum hydrocarbons on the marine environment; a study of the baseline ecology of a proposed OTEC site near Puerto Rico; the environmental impact of offshore geothermal energy development; the movement of radionuclides through the marine environment; the environmental aspects of power plant cooling systems; and studies of the physical and biological oceangraphy of the continental shelves bordering the United States

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

    International Nuclear Information System (INIS)

    1987-03-01

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

  7. MP-Division health and safety reference handbook. [Contains glossary

    Energy Technology Data Exchange (ETDEWEB)

    Putnam, T.M.

    1987-09-01

    This report presents the objectives, organization, policies, and essential rules and procedures that have been adopted by MP Division and that form the basis of the Health and Safety Program of the Clinton P. Anderson Meson Physics Facility (LAMPF). The facility includes the beam-delivery systems for the Los Alamos Neutron Scattering Center and the Weapons Neutron Research Facility (LANSCE/WNR). The program is designed not only to assure the health and safety of all personnel, including users, in their work at LAMPF, and of MP-Division staff in their work on the LANSCE/WNR beam lines, but also to protect the facility (buildings and equipment) and the environment. 33 refs., 18 figs., 2 tabs.

  8. MP-Division health and safety reference handbook

    International Nuclear Information System (INIS)

    Putnam, T.M.

    1987-09-01

    This report presents the objectives, organization, policies, and essential rules and procedures that have been adopted by MP Division and that form the basis of the Health and Safety Program of the Clinton P. Anderson Meson Physics Facility (LAMPF). The facility includes the beam-delivery systems for the Los Alamos Neutron Scattering Center and the Weapons Neutron Research Facility (LANSCE/WNR). The program is designed not only to assure the health and safety of all personnel, including users, in their work at LAMPF, and of MP-Division staff in their work on the LANSCE/WNR beam lines, but also to protect the facility (buildings and equipment) and the environment. 33 refs., 18 figs., 2 tabs

  9. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    International Nuclear Information System (INIS)

    Ferguson, J.B.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance

  10. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1976

    Energy Technology Data Exchange (ETDEWEB)

    Ferguson, J. B. [ed.

    1977-04-01

    Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the effect thermocouples mounted on the outside fuel rod surfaces would have on the departure from nucleate boiling (DNB) phenomena in the LOFT core during steady state operation were completed. A correlation for use in predicting DNB heat fluxes in the LOFT core was developed. Tests of an experimental transit time flowmeter were completed. A nuclear test was performed to obtain fuel rod behavior data from four PWR-type rods during film boiling operation representative of PWR conditions. Preliminary results from the postirradiation examination of Test IE-1 fuel rods are given. Results of Irradiation Effects Tests IE-2 and IE-3 are given. Gap Conductance Test GC 2-1 was performed to evaluate the effects of fuel density, initial gap width, and fill gas composition on the pellet-cladding gap conductance.

  11. Research Award: Donor Partnership Division | IDRC - International ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    2016-09-07

    Sep 7, 2016 ... In the remaining 50% of their time, the Research Award Recipient will contribute to the management of the division through a variety of ... Strong research, analytical, and writing skills, and familiar with website applications.

  12. Safety research programs sponsored by Office of Nuclear Regulatory Research

    International Nuclear Information System (INIS)

    Weiss, A.J.; Azarm, A.; Baum, J.W.

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988

  13. Research Award: Communications Division Deadline: 12 ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Jean-Claude Dumais

    2012-09-12

    Sep 12, 2012 ... IDRC's Communications Division has undertaken a number of initiatives to promote research results to key ... How are new technologies changing the face of publishing and how can development agencies benefit? • How can ...

  14. Environmental Research Division's Data Access Program (ERDDAP)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — ERDDAP (the Environmental Research Division's Data Access Program) is a data server that gives you a simple, consistent way to download subsets of scientific...

  15. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    International Nuclear Information System (INIS)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T

  16. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

  17. Accelerator and fusion research division

    International Nuclear Information System (INIS)

    1992-12-01

    This report contains brief discussions on research topics in the following area: Heavy-Ion Fusion Accelerator Research; Magnetic Fusion Energy; Advanced Light Source; Center for Beam Physics; Superconducting Magnets; and Bevalac Operations

  18. Ontario Hydro Research Division annual report 1988

    International Nuclear Information System (INIS)

    1988-01-01

    The Research Division of Ontario Hydro conducts research in the fields of chemistry, civil engineering, electrical engineering, mechanical engineering, metallurgy, and operations. Much of the research has a bearing on the safe, environmentally benign operation of Ontario Hydro's nuclear power plants. Particular emphasis has been placed on nuclear plant component aging and plant life assurance

  19. The role of the Health and Safety Division of DNPDE

    International Nuclear Information System (INIS)

    Arkley, J.

    1985-01-01

    The paper concerns the role of the Health and Safety Division of the Dounreay Nuclear Power Development Establishment, Scotland. Radiological conditions in the workplace; dosimetry; off-site monitoring; and accidents and emergencies, are all discussed. (U.K.)

  20. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, January--March 1976

    Energy Technology Data Exchange (ETDEWEB)

    Zane, J. O.; Farman, R. F.; Hanson, D. J.; Peterson, A. C.; Ybarrondo, L. J.; Berta, V. T.; Naff, S. A.; Crocker, J. G.; Martinson, Z. R.; Smolik, G. R.; Cawood, G. W.; Quapp, W. J.; Ramsthaler, J. H.; Ransom, V. H.; Scofield, M. P.; Dearien, J. A.; Bohn, M. P.; Burnham, B. W.; James, S. W.; Lee, W. H.; Lime, J. F.; Nalezny, C. L.; MacDonald, P. E.; Thompson, L. B.; Domenico, W. F.; Rice, R. E.; Hendrix, C. E.; Davis, C. B.

    1976-06-01

    Light water reactor sfaety research performed January through March 1976 is summarized. Results of the Semiscale Mod-1 blowdown heat transfer test series relating to those phenomena that influence core fluid and heat transfer effects are analyzed, and preliminary analyses of the recently completed reflood heat transfer test series are summarized for the forced and gravity feed reflood tests. The first nonnuclear LOCE in the LOFT program was successfully completed and preliminary results are presented. Preliminary results are given for the PCM 8-1 RF Test, the PCM-2A Test, and the Irradiation Effects Scoping Test 2 in the Thermal Fuel Behavior Program. Model development and verification efforts reported in the Reactor Behavior Program include checkout of RELAP4/MOD5 Update 1, development of a new hydrodynamic model for two-phase separated flows, development of the RACHET code to assess the assumptions in current fuel behavior codes of uniform stress and strain in the cladding, modifications of the containment code BEACON, analysis of results from the Halden Assembly IFA-429 helium sorption experiment, development of correlations for the thermal conductivity of UO/sub 2/ and (U,Pu)O/sub 2/, and evaluation of RALAP4 through comparison of calculated results with data from the GE Blowdown Heat Transfer and Semiscale experiments.

  1. Research Award: Donor Partnerships Division

    International Development Research Centre (IDRC) Digital Library (Canada)

    Corey Piccioni

    2013-08-07

    Aug 7, 2013 ... IDRC is one of the world's leaders in generang new knowledge to meet global challenges. We offer a number of research awards providing a unique opportunity to enhance research skills and gain a fresh perspecve on crucial development issues. These one‐year, paid, in‐house programs of training and ...

  2. Safety administration division business report. The first quarter of 2002

    International Nuclear Information System (INIS)

    Ishibashi, Takashi

    2002-09-01

    The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these businesses and utilizing the data concerning the businesses, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the first quarter news from April to June in 2002. (author)

  3. Safety administration division business report. The second quarter of 2001

    International Nuclear Information System (INIS)

    Kanamori, Masashi

    2001-12-01

    The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these business and utilizing the data concerning the businesses, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the second quarter news from July to September in 2001. (author)

  4. 2010-11 Research Portfolio: Research & Development Division

    Science.gov (United States)

    Educational Testing Service, 2010

    2010-01-01

    This document describes the breadth of the research that the ETS (Educational Testing Service) Research & Development division is conducting in 2010. This portfolio will be updated in early 2011 to reflect changes to existing projects and new projects that were added after this document was completed. The research described in this portfolio falls…

  5. Progress of nuclear safety research, (1)

    International Nuclear Information System (INIS)

    Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

    1981-01-01

    The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successively in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also, the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts, and in this Part 1, the reactor safety research is described. The safety of nuclear fuel, the integrity and safety of pressure boundary components, the engineered safety in LOCA, fuel behavior in accident and others are reported. (Kako, I.)

  6. Engineering Research Division publication report, calendar year 1980

    International Nuclear Information System (INIS)

    Miller, E.K.; Livingston, P.L.; Rae, D.C.

    1980-06-01

    Each year the Engineering Research Division of the Electronics Engineering Department at Lawrence Livermore Laboratory has issued an internal report listing all formal publications produced by the Division during the calendar year. Abstracts of 1980 reports are presented

  7. Fuel safety research 1999

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-07-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a result of reorganization of the Nuclear Safety Research Center, JAERI. The laboratory was organized by combining three laboratories, the Reactivity Accident Laboratory, the Fuel Reliability Laboratory, and a part of the Sever Accident Research Laboratory. Consequently, the Fuel Safety Research Laboratory is now in charge of all the fuel safety research in JAERI. Various types of experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of five research groups corresponding to each research fields. They are; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). This report summarizes the outline of research activities and major outcomes of the research executed in 1999 in the Fuel Safety Research Laboratory. (author)

  8. Progress of nuclear safety research, (2)

    International Nuclear Information System (INIS)

    Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

    1981-01-01

    The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successevely in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts and in this Part 2, the environmental safety research is described. The evaluation and analysis of environmental radioactivity, the study on radioactive waste management and the studies on various subjects related to environmental safety are reported. (Kako, I.)

  9. Fuel safety research 2000

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a part of reorganization of the Nuclear Safety Research Center, JAERI. The new laboratory was organized by combining three pre-existing laboratories, Reactivity Accident Laboratory, Fuel Reliability Laboratory, and a part of Severe Accident Research Laboratory. The Fuel Safety Research Laboratory becomes to be in charge of all fuel safety research in JAERI. Various experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of following five research groups corresponding to each research fields; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). The research activities in year 2000 produced many important data and information. They are, for example, failure of high burnup BWR fuel rod under RIA conditions, data on the behavior of hydrided Zircaloy cladding under LOCA conditions and FP release data from VEGA experiments at very high temperature/pressure condition. This report summarizes the outline of research activities and major outcomes of the research executed in 2000 in the Fuel Safety Research Laboratory. (author)

  10. 78 FR 28630 - Pfizer Therapeutic Research, Pfizer Worldwide Research & Development Division, Formerly Known as...

    Science.gov (United States)

    2013-05-15

    ... Research, Pfizer Worldwide Research & Development Division, Formerly Known as Warner Lambert Company... Groton, Connecticut location of Pfizer Therapeutic Research, Pfizer Worldwide Research & Development... Worldwide Research & Development Division, formerly known as Warner Lambert Company, Comparative Medicine...

  11. Fuel safety research 2001

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    The Fuel Safety Research Laboratory is in charge of research activity which covers almost research items related to fuel safety of water reactor in JAERI. Various types of experimental and analytical researches are being conducted by using some unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and the Reactor Fuel Examination Facility (RFEF) of JAERI. The research to confirm the safety of high burn-up fuel and MOX fuel under accident conditions is the most important item among them. The laboratory consists of following five research groups corresponding to each research fields; Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). Research group of fuel behavior analysis (FEMAXI group). Research group of radionuclides release and transport behavior from irradiated fuel under severe accident conditions (VEGA group). The research conducted in the year 2001 produced many important data and information. They are, for example, the fuel behavior data under BWR power oscillation conditions in the NSRR, the data on failure-bearing capability of hydrided cladding under LOCA conditions and the FP release data at very high temperature in steam which simulate the reactor core condition during severe accidents. This report summarizes the outline of research activities and major outcomes of the research executed in 2001 in the Fuel Safety Research Laboratory. (author)

  12. Nuclear safety research

    International Nuclear Information System (INIS)

    1999-01-01

    The NNSA checked and coordinated in 1999 the research project of the Surveillance Technology on Nuclear Installations under the National 9th-Five-Year Program to promote the organizations that undertake the research work on schedule and lay a foundation of obtaining achievements and effectiveness for the 9th-five-year plan on nuclear safety research

  13. High energy physics division semiannual report of research activities

    International Nuclear Information System (INIS)

    Schoessow, P.; Moonier, P.; Talaga, R.; Wagner, R.

    1991-08-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1991--June 30, 1991. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  14. Chemical Engineering Division research highlights, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Burris, L.; Webster, D. S.; Barney, D. L.; Cafasso, F. A.; Steindler, M. J.

    1980-06-01

    In 1979, CEN conducted research and development in the following areas: (1) high-temperature, rechargeable lithium/iron sulfide batteries for electric vehicles and electric utility load leveling; (2) ambient-temperature batteries - improved lead-acid, nickel/zinc, and nickel/iron - for electric vehicles; (3) molten carbonate fuel cells for use by electric utilities; (4) coal technology - mainly fluidized-bed combustion of coal in the presence of SO/sub 2/ sorbent of limestone; (5) heat- and seed- recovery technology for open-cycle magnetohydrodynamic systems; (6) solar energy collectors and thermal energy storage; (7) fast breeder reactor chemistry research - chemical support of reactor safety studies, chemistry of irradiated fuels, and sodium technology; (8) fuel cycle technology - reprocessing of nuclear fuels, management of nuclear wastes, geologic migration studies, and proof-of-breeding studies for the Light Water Breeder Reactor; (9) magnetic fusion research - lithium processing technology and materials research; and (10) basic energy sciences - homogeneous catalysis, thermodynamics of inorganic and organic materials, environmental chemistry, electrochemistry, and physical properties of salt vapors. Separate abstracts were prepared for each of these areas.

  15. Quarterly report on the activities in Safety Administration Division. The second quarter of 2003

    International Nuclear Information System (INIS)

    Yamamoto, Junta

    2004-08-01

    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, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in July to September in 2003. (author)

  16. 78 FR 48468 - Delphi Corporation, Electronics and Safety Division, Including On-Site Leased Workers From...

    Science.gov (United States)

    2013-08-08

    ..., Electronics and Safety Division, Including On-Site Leased Workers From Securitas, Bartech, Flint Janitorial... Adjustment Assistance on May 20, 2013, applicable to workers of Delphi Corporation, Electronics and Safety... on- site at the Flint, Michigan location of Delphi Corporation, Electronics and Safety Division. The...

  17. Quarterly report on the activities in safety Administration Division. The forth quarter of 2003

    International Nuclear Information System (INIS)

    Yamamoto, Junta

    2005-01-01

    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, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in January to March in 2004. (author)

  18. Quarterly report on the activities in Safety Administration Division. The fourth quarter of 2002

    International Nuclear Information System (INIS)

    Yamamoto, Junta

    2003-11-01

    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, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in January to March in 2003. (author)

  19. Safety administration division business report. The second quarter of 2002. Document on present state of affairs

    International Nuclear Information System (INIS)

    Ishibashi, Takashi

    2003-02-01

    The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a labor safety health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in July to September in 2002. (author)

  20. Quarterly report on the activities in Safety Administration Division. The first quarter of 2003

    International Nuclear Information System (INIS)

    Yamamoto, Junta

    2004-02-01

    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, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in April to June in 2003. (author)

  1. Nuclear Safety Research Review Committee

    International Nuclear Information System (INIS)

    Todreas, N.E.

    1990-01-01

    The Nuclear Safety Research Review Committee has had a fundamental difficulty because of the atmosphere that has existed since it was created. It came into existence at a time of decreasing budgets. For any Committee the easiest thing is to tell the Director what additional to do. That does not really help him a lot in this atmosphere of reduced budgets which he reviewed for you on Monday. Concurrently the research arm of Nuclear Regulatory Commission has recognized that the scope of its activity needed to be increased rather than decreased. In the last two-and-a-half-year period, human factors work was reinstated, radiation and health effects investigations were reinvigorated, research in the waste area was given significant acceleration. Further, accident management came into being, and the NRC finally got back into the TMI-2 area. So with all of those activities being added to the program at the same time that the research budget was going down, the situation has become very strained. What that leads to regarding Committee membership is a need for technically competent generalists who will be able to sit as the Division Directors come in, as the contractors come in, and sort the wheat from the chaff. The Committee needs people who are interested in and have a broad perspective on what regulatory needs are and specifically how safety research activities can contribute to them. The author summarizes the history of the Committee, the current status, and plans for the future

  2. Safety of Research Reactors. Safety Requirements

    International Nuclear Information System (INIS)

    2010-01-01

    The main objective of this Safety Requirements publication is to provide a basis for safety and a basis for safety assessment for all stages in the lifetime of a research reactor. Another objective is to establish requirements on aspects relating to regulatory control, the management of safety, site evaluation, design, operation and decommissioning. Technical and administrative requirements for the safety of research reactors are established in accordance with these objectives. This Safety Requirements publication is intended for use by organizations engaged in the site evaluation, design, manufacturing, construction, operation and decommissioning of research reactors as well as by regulatory bodies

  3. Earth Sciences Division, collected abstracts-1977. [Research programs

    Energy Technology Data Exchange (ETDEWEB)

    Quitiquit, W.A.; Ledbetter, G.P.; Henry, A.L.

    1978-05-24

    This report is a compilation of abstracts of papers, internal reports, and talks presented during 1977 at national and international meetings by members of the Earth Sciences Division, Lawrence Livermore Laboratory. It is arranged alphabetically by author and includes a cross-reference by subject indicating the areas of research interest of the Earth Sciences Division.

  4. 77 FR 65582 - Pfizer Therapeutic Research, Pfizer Worldwide Reasearch & Development Division, Formerly Known as...

    Science.gov (United States)

    2012-10-29

    ... Research, Pfizer Worldwide Reasearch & Development Division, Formerly Known as Warner Lambert Company... workers of Pfizer Therapeutic Research, Pfizer Worldwide Research & Development Division, formerly known... follows: All workers of Pfizer Therapeutic Research, Pfizer Worldwide Research & Development Division...

  5. Nuclear safety research

    International Nuclear Information System (INIS)

    1996-01-01

    The topics 'Large-sized PWR-NPP Safety Techniques Research',and 'The Key Techniques Research on the Safety Supervision and Control for Operation of Nuclear Installations' have been adopted as an apart of 'the National 9th five Year Programs for Tacking the Key Scientific and Technical Topics' which are organized by the State Planning Commission (SPC) and State Science and Technology Commission (SSTC) respectively, and have obtained a financial support from them. To play a better role with the limited fund, the NNSA laid special stress on selecting key sub-topics on nuclear safety, and carefully choosing units which would undertake sub-topics and signing technical contracts with them

  6. Environmental Research Division technical progress report: January 1986--October 1987

    International Nuclear Information System (INIS)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter. Individual projects under each division are processed separately for the data bases

  7. Environmental Research Division technical progress report: January 1986--October 1987

    Energy Technology Data Exchange (ETDEWEB)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter. Individual projects under each division are processed separately for the data bases.

  8. Current research in Radiation Biology and Biochemistry Division

    International Nuclear Information System (INIS)

    Tarachand, U.; Singh, B.B.

    1995-01-01

    The Radiation Biology and Biochemistry Division, Bhabha Atomic Research Centre, Bombay has been engaged in research in the frontier areas of (i) radiation biology related to tumour therapy and injury caused by free radicals; (ii) molecular basis of diseases of physiological origin; (iii) molecular aspects of chemical carcinogenesis and (iv) structure of genome and genome related functions. The gist of research and development activities carried out in the Division during the last two years are documented

  9. Current research in Radiation Biology and Biochemistry Division

    Energy Technology Data Exchange (ETDEWEB)

    Tarachand, U; Singh, B B [eds.; Bhabha Atomic Research Centre, Bombay (India). Radiation Biology and Biochemistry Div.

    1996-12-31

    The Radiation Biology and Biochemistry Division, Bhabha Atomic Research Centre, Bombay has been engaged in research in the frontier areas of (i) radiation biology related to tumour therapy and injury caused by free radicals; (ii) molecular basis of diseases of physiological origin; (iii) molecular aspects of chemical carcinogenesis and (iv) structure of genome and genome related functions. The gist of research and development activities carried out in the Division during the last two years are documented.

  10. Operational safety reliability research

    International Nuclear Information System (INIS)

    Hall, R.E.; Boccio, J.L.

    1986-01-01

    Operating reactor events such as the TMI accident and the Salem automatic-trip failures raised the concern that during a plant's operating lifetime the reliability of systems could degrade from the design level that was considered in the licensing process. To address this concern, NRC is sponsoring the Operational Safety Reliability Research project. The objectives of this project are to identify the essential tasks of a reliability program and to evaluate the effectiveness and attributes of such a reliability program applicable to maintaining an acceptable level of safety during the operating lifetime at the plant

  11. Researches in nuclear safety

    International Nuclear Information System (INIS)

    Souchet, Y.

    2009-01-01

    This article comprises three parts: 1 - some general considerations aiming at explaining the main motivations of safety researches, and at briefly presenting the important role of some organisations in the international conciliation, and the most common approach used in safety researches (analytical experiments, calculation codes, global experiments); 2 - an overview of some of the main safety problems that are the object of worldwide research programs (natural disasters, industrial disasters, criticality, human and organisational factors, fuel behaviour in accidental situation, serious accidents: core meltdown, corium spreading, failure of the confinement building, radioactive releases). Considering the huge number of research topics, this part cannot be exhaustive and many topics are not approached; 3 - the presentation of two research programs addressing very different problems: the evaluation of accidental releases in the case of a serious accident (behaviour of iodine and B 4 C, air infiltration, fission products release) and the propagation of a fire in a facility (PRISME program). These two programs belong to an international framework involving several partners from countries involved in nuclear energy usage. (J.S.)

  12. Engineering Research Division report on reports: calendar year 1979

    International Nuclear Information System (INIS)

    Gardner, C.L.; Johnston, S.J.

    1980-03-01

    A bibliography of publications of members of the Engineering Research Division of the Electronics Engineering Department is presented for 1979. Abstracts for 148 publications are included, along with author and keywork indexes

  13. Earth Sciences Division Research Summaries 2002-2003

    Energy Technology Data Exchange (ETDEWEB)

    Bodvarsson, G.S.

    2003-11-01

    Research in earth and atmospheric sciences is becoming increasingly important in light of the energy, climate change, and environmental issues facing the United States and the world. The development of new energy resources other than hydrocarbons and the safe disposal of nuclear waste and greenhouse gases (such as carbon dioxide and methane) are critical to the future energy needs and environmental safety of this planet. In addition, the cleanup of many contaminated sites in the U.S., along with the preservation and management of our water supply, remain key challenges for us as well as future generations. Addressing these energy, climate change, and environmental issues requires the timely integration of earth sciences' disciplines (such as geology, hydrology, oceanography, climatology, geophysics, geochemistry, geomechanics, ecology, and environmental sciences). This integration will involve focusing on fundamental crosscutting concerns that are common to many of these issues. A primary focus will be the characterization, imaging, and manipulation of fluids in the earth. Such capabilities are critical to many DOE applications, from environmental restoration to energy extraction and optimization. The Earth Sciences Division (ESD) of the Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) is currently addressing many of the key technical issues described above. In this document, we present summaries of many of our current research projects. While it is not a complete accounting, it is representative of the nature and breadth of our research effort. We are proud of our scientific efforts, and we hope that you will find our research useful and exciting. Any comments on our research are appreciated and can be sent to me personally. This report is divided into five sections that correspond to the major research programs in the Earth Sciences Division: (1) Fundamental and Exploratory Research; (2) Nuclear Waste; (3) Energy Resources; (4

  14. Earth Sciences Division Research Summaries 2002-2003

    International Nuclear Information System (INIS)

    Bodvarsson, G.S.

    2003-01-01

    Research in earth and atmospheric sciences is becoming increasingly important in light of the energy, climate change, and environmental issues facing the United States and the world. The development of new energy resources other than hydrocarbons and the safe disposal of nuclear waste and greenhouse gases (such as carbon dioxide and methane) are critical to the future energy needs and environmental safety of this planet. In addition, the cleanup of many contaminated sites in the U.S., along with the preservation and management of our water supply, remain key challenges for us as well as future generations. Addressing these energy, climate change, and environmental issues requires the timely integration of earth sciences' disciplines (such as geology, hydrology, oceanography, climatology, geophysics, geochemistry, geomechanics, ecology, and environmental sciences). This integration will involve focusing on fundamental crosscutting concerns that are common to many of these issues. A primary focus will be the characterization, imaging, and manipulation of fluids in the earth. Such capabilities are critical to many DOE applications, from environmental restoration to energy extraction and optimization. The Earth Sciences Division (ESD) of the Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) is currently addressing many of the key technical issues described above. In this document, we present summaries of many of our current research projects. While it is not a complete accounting, it is representative of the nature and breadth of our research effort. We are proud of our scientific efforts, and we hope that you will find our research useful and exciting. Any comments on our research are appreciated and can be sent to me personally. This report is divided into five sections that correspond to the major research programs in the Earth Sciences Division: (1) Fundamental and Exploratory Research; (2) Nuclear Waste; (3) Energy Resources; (4) Environmental

  15. Research Award: CommunicaƟons Division

    International Development Research Centre (IDRC) Digital Library (Canada)

    Corey Piccioni

    The Communicaons Research Award focuses on corporate and research communicaon ... social media strategies, as well as other outreach programs. ... enrolled at a recognized university at the master's or doctoral level or have completed a.

  16. Accelerator and Fusion Research Division 1989 summary of activities

    International Nuclear Information System (INIS)

    1990-06-01

    This report discusses the research being conducted at Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division. The main topics covered are: heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; high-energy physics technology; and bevalac operations

  17. Accelerator and Fusion Research Division 1989 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1990-06-01

    This report discusses the research being conducted at Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division. The main topics covered are: heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; high-energy physics technology; and bevalac operations.

  18. HTGR safety research program

    International Nuclear Information System (INIS)

    Barsell, A.W.; Olsen, B.E.; Silady, F.A.

    1981-01-01

    An HTGR safety research program is being performed supporting and guided in priorities by the AIPA Probabilistic Risk Study. Analytical and experimental studies have been conducted in four general areas where modeling or data assumptions contribute to large uncertainties in the consequence assessments and thus, in the risk assessment for key core heat-up accident scenarios. Experimental data have been obtained on time-dependent release of fission products from the fuel particles, and plateout characteristics of condensible fission products in the primary circuit. Potential failure modes of primarily top head PCRV components as well as concrete degradation processes have been analyzed using a series of newly developed models and interlinked computer programs. Containment phenomena, including fission product deposition and potential flammability of liberated combustible gases have been studied analytically. Lastly, the behaviour of boron control material in the core and reactor subcriticality during core heatup have been examined analytically. Research in these areas has formed the basis for consequence updates in GA-A15000. Systematic derivation of future safety research priorities is also discussed. (author)

  19. Environmental Research Division technical progress report, January 1984-December 1985

    International Nuclear Information System (INIS)

    1986-05-01

    Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter

  20. Environmental Research Division technical progress report, January 1984-December 1985

    Energy Technology Data Exchange (ETDEWEB)

    1986-05-01

    Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter.

  1. Mol - Research Division Report 1986 - 2

    International Nuclear Information System (INIS)

    Delbarre, J.

    1987-03-01

    This report covers the research activities carried out at the SCK-CEN, Mol during the second semester of 1986. It deals with chemistry, chemical engineering, biology, nuclear metrology, analytical chemistry. (MCB)

  2. Mol - Research Division report 1987 - 2

    International Nuclear Information System (INIS)

    Delbarre, J.

    1988-03-01

    This report covers the research activities at the SCK-CEN, MOl, during the second semester of 1987. It deals with materials physics, nuclear physics, metallurgy, ceramics, nuclear chemistry, chemical engineering, biology, nuclear metrology and analytical chemistry. (MCB)

  3. Mol - Research Division Report 1986 - 1

    International Nuclear Information System (INIS)

    Delbarre, J.; Assche, P. van

    1986-11-01

    This report covers the research activities carried out at the SCK-CEN, Mol from the middle of 1985 till mid 1986. It deals with materials science, metallurgy, ceramics, nuclear chemistry, chemical engineering, biology, nuclear meteorology and analytical chemistry. (MCB)

  4. Mol - Research Division report 1987 - 1

    International Nuclear Information System (INIS)

    Delbarre, J.

    1987-10-01

    This report covers the research activities at the SCK-CEN, Mol, during the first semester of 1987. It deals with material physics, nuclear physics, metallurgy, ceramics, nuclear chemistry, chemical engineering, biology, nuclear metrology and analytical chemistry. (MCB)

  5. Plasma research in the thermodynamics division

    International Nuclear Information System (INIS)

    Gorczyca, B.; Sado, J.

    1995-01-01

    In this state some recent research concerning the theoretical and experimental investigations of low- and high-temperature plasmas was done. The model of LTE and non-LTE was used to descriptions of plasma conditions. The non-LTE assumptions were applied to two-temperature state of plasmas and to the ionizational nonequilibrium. The result of the research was the analysis of the transport phenomena in isotropic and anisotropic plasmas, where anisotropic was done by the external electric or magnetic fields. The experimental part of the research concerned the plasma measurement methods, particularly applied to the Klein effect, the spectroscopic methods and the laser diagnostics of plasma. Some research studied the interactions between strong magnetic field and injected gas flux to a reactor. This is the fundamental problem in controlled fission processes (the high-temperature plasma). (author). 9 refs, 12 figs

  6. Nutrition and Cancer Prevention Research Practicum | Division of Cancer Prevention

    Science.gov (United States)

    The Nutritional Science Research Group in the Division of Cancer Prevention at the National Cancer Institute, National Institutes of Health and the Department of Nutrition at the Clinical Center, National Institutes of Health are offering a one week educational opportunity in "Nutrition and Cancer Prevention Research" for individuals with a sustained commitment to nutrition

  7. RESEARCH ACTIVITIES AT THE US EPA'S GULF ECOLOGY DIVISION

    Science.gov (United States)

    The purpose of this talk was to present an overview of research activities at the US EPA's Office of Research and Development, Gulf Ecology Division located on Pensacola Beach, Florida. The talk was organized into three major sections. The first section covered my educational b...

  8. Quarterly report of Biological and Medical Research Division, April 1955

    Energy Technology Data Exchange (ETDEWEB)

    Brues, A.M.

    1955-04-01

    This report is a compilation of 48 investigator prepared summaries of recent progress in individual research programs of the Biology and Medical Division of the Argonne National Laboratory for the quarterly period ending April,1955. Individual reports are about 3-6 pages in length and often contain research data.

  9. Earth Sciences Division Research Summaries 2006-2007

    International Nuclear Information System (INIS)

    DePaolo, Donald; DePaolo, Donald

    2008-01-01

    Research in earth and atmospheric sciences has become increasingly important in light of the energy, climate change, and other environmental issues facing the United States and the world. The development of new energy resources other than fossil hydrocarbons, the safe disposal of nuclear waste and greenhouse gases, and a detailed understanding of the climatic consequences of our energy choices are all critical to meeting energy needs while ensuring environmental safety. The cleanup of underground contamination and the preservation and management of water supplies continue to provide challenges, as they will for generations into the future. To address the critical energy and environmental issues requires continuing advances in our knowledge of Earth systems and our ability to translate that knowledge into new technologies. The fundamental Earth science research common to energy and environmental issues largely involves the physics, chemistry, and biology of fluids in and on the Earth. To manage Earth fluids requires the ability to understand their properties and behavior at the most fundamental molecular level, as well as prediction, characterization, imaging, and manipulation of those fluids and their behavior in real Earth reservoirs. The broad range of disciplinary expertise, the huge range of spatial and time scales, and the need to integrate theoretical, computational, laboratory and field research, represent both the challenge and the excitement of Earth science research. The Earth Sciences Division (ESD) of the Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) is committed to addressing the key scientific and technical challenges that are needed to secure our energy future in an environmentally responsibly way. Our staff of over 200 scientists, UC Berkeley faculty, support staff and guests perform world-acclaimed fundamental research in hydrogeology and reservoir engineering, geophysics and geomechanics, geochemistry, microbial ecology

  10. Earth Sciences Division Research Summaries 2006-2007

    Energy Technology Data Exchange (ETDEWEB)

    DePaolo, Donald; DePaolo, Donald

    2008-07-21

    Research in earth and atmospheric sciences has become increasingly important in light of the energy, climate change, and other environmental issues facing the United States and the world. The development of new energy resources other than fossil hydrocarbons, the safe disposal of nuclear waste and greenhouse gases, and a detailed understanding of the climatic consequences of our energy choices are all critical to meeting energy needs while ensuring environmental safety. The cleanup of underground contamination and the preservation and management of water supplies continue to provide challenges, as they will for generations into the future. To address the critical energy and environmental issues requires continuing advances in our knowledge of Earth systems and our ability to translate that knowledge into new technologies. The fundamental Earth science research common to energy and environmental issues largely involves the physics, chemistry, and biology of fluids in and on the Earth. To manage Earth fluids requires the ability to understand their properties and behavior at the most fundamental molecular level, as well as prediction, characterization, imaging, and manipulation of those fluids and their behavior in real Earth reservoirs. The broad range of disciplinary expertise, the huge range of spatial and time scales, and the need to integrate theoretical, computational, laboratory and field research, represent both the challenge and the excitement of Earth science research. The Earth Sciences Division (ESD) of the Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) is committed to addressing the key scientific and technical challenges that are needed to secure our energy future in an environmentally responsibly way. Our staff of over 200 scientists, UC Berkeley faculty, support staff and guests perform world-acclaimed fundamental research in hydrogeology and reservoir engineering, geophysics and geomechanics, geochemistry, microbial ecology

  11. Chemical Engineering Division research highlights, 1977

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-08-01

    Separate abstracts are included for sections with information on lithium/metal sulfide batteries; electrochemical energy development; advanced fuel cell development; utilization of coal; magnetohydrodynamics technology; LMFBR and GCFR support work; fuel cycle studies; fusion reactor research; solar energy development; and basic energy science.

  12. Accelerator ampersand Fusion Research Division: 1993 Summary of activities

    International Nuclear Information System (INIS)

    Chew, J.

    1994-04-01

    The Accelerator and Fusion Research Division (AFRD) is not only one of the largest scientific divisions at LBL, but also the one of the most diverse. Major efforts include: (1) investigations in both inertial and magnetic fusion energy; (2) operation of the Advanced Light Source, a state-of-the-art synchrotron radiation facility; (3) exploratory investigations of novel radiation sources and colliders; (4) research and development in superconducting magnets for accelerators and other scientific and industrial applications; and (5) ion beam technology development for nuclear physics and for industrial and biomedical applications. Each of these topics is discussed in detail in this book

  13. Accelerator & Fusion Research Division: 1993 Summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    Chew, J.

    1994-04-01

    The Accelerator and Fusion Research Division (AFRD) is not only one of the largest scientific divisions at LBL, but also the one of the most diverse. Major efforts include: (1) investigations in both inertial and magnetic fusion energy; (2) operation of the Advanced Light Source, a state-of-the-art synchrotron radiation facility; (3) exploratory investigations of novel radiation sources and colliders; (4) research and development in superconducting magnets for accelerators and other scientific and industrial applications; and (5) ion beam technology development for nuclear physics and for industrial and biomedical applications. Each of these topics is discussed in detail in this book.

  14. Environmental Sciences Division: Summaries of research in FY 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    This document describes the Fiscal Year 1996 activities and products of the Environmental Sciences Division, Office of Biological and Environmental Research, Office of Energy Research. The report is organized into four main sections. The introduction identifies the basic program structure, describes the programs of the Environmental Sciences Division, and provides the level of effort for each program area. The research areas and project descriptions section gives program contact information, and provides descriptions of individual research projects including: three-year funding history, research objective and approach used in each project, and results to date. Appendixes provide postal and e-mail addresses for principal investigators and define acronyms used in the text. The indexes provide indexes of principal investigators, research institutions, and keywords for easy reference. Research projects are related to climatic change and remedial action.

  15. Safety analysis for research reactors

    International Nuclear Information System (INIS)

    2008-01-01

    The aim of safety analysis for research reactors is to establish and confirm the design basis for items important to safety using appropriate analytical tools. The design, manufacture, construction and commissioning should be integrated with the safety analysis to ensure that the design intent has been incorporated into the as-built reactor. Safety analysis assesses the performance of the reactor against a broad range of operating conditions, postulated initiating events and other circumstances, in order to obtain a complete understanding of how the reactor is expected to perform in these situations. Safety analysis demonstrates that the reactor can be kept within the safety operating regimes established by the designer and approved by the regulatory body. This analysis can also be used as appropriate in the development of operating procedures, periodic testing and inspection programmes, proposals for modifications and experiments and emergency planning. The IAEA Safety Requirements publication on the Safety of Research Reactors states that the scope of safety analysis is required to include analysis of event sequences and evaluation of the consequences of the postulated initiating events and comparison of the results of the analysis with radiological acceptance criteria and design limits. This Safety Report elaborates on the requirements established in IAEA Safety Standards Series No. NS-R-4 on the Safety of Research Reactors, and the guidance given in IAEA Safety Series No. 35-G1, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, providing detailed discussion and examples of related topics. Guidance is given in this report for carrying out safety analyses of research reactors, based on current international good practices. The report covers all the various steps required for a safety analysis; that is, selection of initiating events and acceptance criteria, rules and conventions, types of safety analysis, selection of

  16. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J; Azarm, A; Baum, J W; Boccio, J L; Carew, J; Diamond, D J; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Haber, S B

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988.

  17. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Baum, J W; Boccio, J L; Diamond, D; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Hall, R E; Higgins, J C; Weiss, A J [comp.

    1988-12-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987.

  18. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

    International Nuclear Information System (INIS)

    Baum, J.W.; Boccio, J.L.; Diamond, D.

    1988-12-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987

  19. Prospects for nuclear safety research

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-04-01

    This document is the text of a paper presented by Eric S. Beckjord (Director, Nuclear Regulatory Research/NRC) at the 22nd Water Reactor Safety Meeting in Bethesda, MD in October 1994. The following topics are briefly reviewed: (1) Reactor vessel research, (2) Probabilistic risk assessment, (3) Direct containment heating, (4) Advanced LWR research, (5) Nuclear energy prospects in the US, and (6) Future nuclear safety research. Subtopics within the last category include economics, waste disposal, and health and safety.

  20. Barrett's Esophagus Translational Research Network (BETRNet) | Division of Cancer Prevention

    Science.gov (United States)

    The goal of BETRNet is to reduce the incidence, morbidity, and mortality of esophageal adenocarcinoma by answering key questions related to the progression of the disease, especially in the premalignant stage. In partnership with NCI’s Division of Cancer Biology, multidisciplinary translational research centers collaborate to better understand the biology of Barrett's

  1. Japan Atomic Energy Research Institute, Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1981-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1980 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  2. Japan Atomic Energy Research Institute, Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1979-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1978 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committees on Reactor Physics and in Decommissioning of Nuclear Facilities. (author)

  3. Accelerator and Fusion Research Division: Summary of activities, 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This report contains a summary of activities at the Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division for the year 1986. Topics and facilities investigated in individual papers are: 1-2 GeV Synchrotron Radiation Source, the Center for X-Ray Optics, Accelerator Operations, High-Energy Physics Technology, Heavy-Ion Fusion Accelerator Research and Magnetic Fusion Energy. Six individual papers have been indexed separately

  4. Research at WNRE

    International Nuclear Information System (INIS)

    Johnson, H.M.

    1986-01-01

    A broad overview of the structure and research of Whiteshell Nuclear Research Establishment (WNRE) is presented. The research programs are divided amongst four divisions and a new business project: Waste Management Division, Applied Science Division, Chemistry and Materials Science Division, Mini-Reactor Business, and the Health and Safety Division. All divisions are briefly described. Emphasis is placed upon the Health and Safety division

  5. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A J [comp.

    1989-02-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs.

  6. Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1989-02-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs

  7. Safety research program of NUCEF

    International Nuclear Information System (INIS)

    Naito, Y.

    1996-01-01

    To contribute the safety and establishment of advanced technologies in the area of nuclear fuel cycle, Japan Atomic Energy Research Institute (JAERI) has constructed a new research facility NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) as the center for the research and development, particularly on the reprocessing technology and transuranium (TRU) waste management. NUCEF consist of three buildings, administration building, experiment building A and B. Building A has two experiment facilities STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility). The experiment building B is referred to as BECKY (Back-end Fuel Cycle Key Elements Research Facility). Researches on the reprocessing and the waste management are carried out with spent fuels, high-level liquid waste, TRU etc. in the α γ cell and glove boxes. NUCEF was constructed with the following aims. Using STACY and TRACY, are aimed, (1) research on advanced technology for criticality safety control, (2) reconfirmation of criticality safety margin of the Rokkasho reprocessing plant. Using BECKY, are aimed, (1) research on advanced technology of reprocessing process, (2) contribution to develop the scenario for TRU waste disposal, (3) development of new technology for TRU partitioning and volume reduction of radioactive waste. To realize the above aims, following 5 research subjects are settled in NUCEF, (1) Criticality safety research, (2) Research on safety and advanced technology of fuel reprocessing, (3) Research on TRU waste management, (4) Fundamental research on TRU chemistry, (5) Key technology development for TRU processing. (author)

  8. 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

  9. Materials and Components Technology Division research summary, 1992

    International Nuclear Information System (INIS)

    1992-11-01

    The Materials and Components Technology Division (MCT) provides a research and development capability for the design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs related to nuclear energy support the development of the Integral Fast Reactor (IFR): life extension and accident analyses for light water reactors (LWRs); fuels development for research and test reactors; fusion reactor first-wall and blanket technology; and safe shipment of hazardous materials. MCT Conservation and Renewables programs include major efforts in high-temperature superconductivity, tribology, nondestructive evaluation (NDE), and thermal sciences. Fossil Energy Programs in MCT include materials development, NDE technology, and Instrumentation design. The division also has a complementary instrumentation effort in support of Arms Control Technology. Individual abstracts have been prepared for the database

  10. Nuclear safety research master plan

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

    2001-06-01

    The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

  11. Compilation of contract research for the Materials Engineering Branch, Division of Engineering: Annual report for FY 1987

    International Nuclear Information System (INIS)

    1988-06-01

    This compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators, nondestructive examination of primary components, and in safety research for decommissioning and decontamination, on-site storage, and engineered safety features. This report, covering research conducted during Fiscal Year 1987 is the sixth volume of the series of NUREG-0975, ''Compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering.''

  12. Quarterly report on the activities in safety administration division. The third quarter of 2002. Document on present state of affairs

    International Nuclear Information System (INIS)

    Ishibashi, Takashi

    2003-06-01

    The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a labor safety health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in October to December in 2002. (author)

  13. 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)

  14. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    1982-09-01

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.) [de

  15. Engineering Research Division report on reports calendar year 1978

    International Nuclear Information System (INIS)

    Lorton, M.E.

    1979-01-01

    Each year the Engineering Research Division of the Electronics Engineering Department has issued an internal report listing of all formal publications produced by the division during the calendar year. The report for 1978 is being issued in two sections (the second section has been expanded from the former format due to a change in collection of information implemented during the calendar year 1978). The first section (covering January 1978 through June 1978) lists the titles, report numbers, authors, dates, an author index, and, when applicable, conferences or journals to which the paper was submitted. The second section (covering July 1978 through December 1978) provides, in addition to the above information, abstracts for each paper, and an appendix with keywords. Future publication reports will include abstracts and a keyword appendix for all reports. It is expected that the new format will make the publication report a more useful document

  16. Accelerator and Fusion Research Division: summary of activities, 1983

    International Nuclear Information System (INIS)

    1984-08-01

    The activities described in this summary of the Accelerator and Fusion Research Division are diverse, yet united by a common theme: it is our purpose to explore technologically advanced techniques for the production, acceleration, or transport of high-energy beams. These beams may be the heavy ions of interest in nuclear science, medical research, and heavy-ion inertial-confinement fusion; they may be beams of deuterium and hydrogen atoms, used to heat and confine plasmas in magnetic fusion experiments; they may be ultrahigh-energy protons for the next high-energy hadron collider; or they may be high-brilliance, highly coherent, picosecond pulses of synchrotron radiation

  17. Technology Development, Evaluation, and Application (TDEA) FY 2001 Progress Report Environment, Safety, and Health (ESH) Division

    Energy Technology Data Exchange (ETDEWEB)

    L.G. Hoffman; K. Alvar; T. Buhl; E. Foltyn; W. Hansen; B. Erdal; P. Fresquez; D. Lee; B. Reinert

    2002-05-01

    This progress report presents the results of 11 projects funded ($500K) in FY01 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division (ESH). Five projects fit into the Health Physics discipline, 5 projects are environmental science and one is industrial hygiene/safety. As a result of their TDEA-funded projects, investigators have published sixteen papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplement funds and in-kind contributions, such as staff time, instrument use, and workspace, were also provided to TDEA-funded projects by organizations external to ESH Divisions.

  18. Environment, Health and Safety (EH&S): Division Liaisons

    Science.gov (United States)

    . Israel Tadesse Chemical Sciences x4043 Cell: 610-0856 Maram Kassis Electronic waste (E-waste) pickup or Source Representative 2231, 2014 Scott E. Taylor Chemical Safety Subcommittee Chairperson 4103 Hendrik Representative 7457 Stephen M. Franaszek Genomics Representative 925-296-5807 Vera Potapenko Marcia Ocon Leimer

  19. Research program on regulatory safety research

    International Nuclear Information System (INIS)

    Mailaender, R.

    2010-02-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning regulatory nuclear safety research, as co-ordinated by the Swiss Nuclear Safety Inspectorate ENSI. Work carried out in various areas is reviewed, including that done on reactor safety, radiation protection and waste disposal as well as human aspects, organisation and safety culture. Work done concerning materials, pressure vessel integrity, transient analysis, the analysis of serious accidents in light-water reactors, fuel and material behaviour, melt cooling and concrete interaction is presented. OECD data bank topics are discussed. Transport and waste disposal research at the Mont Terri rock laboratory is looked at. Requirements placed on the personnel employed in nuclear power stations are examined and national and international co-operation is reviewed

  20. IAEA activities in the field of research reactors safety

    International Nuclear Information System (INIS)

    Ciuculescu, C.; Boado Magan, H.J.

    2004-01-01

    IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

  1. Seismic safety research program plan

    International Nuclear Information System (INIS)

    1985-06-01

    This plan describes the safety issues, regulatory needs, and the research necessary to address these needs. The plan also discusses the relationship between current and proposed research within the NRC and research sponsored by other government agencies, universities, industry groups, professional societies, and foreign sources

  2. 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

  3. Materials and Components Technology Division research summary, 1991

    International Nuclear Information System (INIS)

    1991-04-01

    This division has the purpose of providing a R and D capability for design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs are in support of the Integral Fast Reactor, life extension for light water reactors, fuels development for the new production reactor and research and test reactors, fusion reactor first-wall and blanket technology, safe shipment of hazardous materials, fluid mechanics/materials/instrumentation for fossile energy systems, and energy conservation and renewables (including tribology, high- temperature superconductivity). Separate abstracts have been prepared for the data base

  4. Biomedical Research Group, Health Division annual report 1954

    Energy Technology Data Exchange (ETDEWEB)

    Langham, W.H.; Storer, J.B.

    1955-12-31

    This report covers the activities of the Biomedical Research Group (H-4) of the Health Division during the period January 1 through December 31, 1954. Organizationally, Group H-4 is divided into five sections, namely, Biochemistry, Radiobiology, Radiopathology, Biophysics, and Organic Chemistry. The activities of the Group are summarized under the headings of the various sections. The general nature of each section`s program, publications, documents and reports originating from its members, and abstracts and summaries of the projects pursued during the year are presented.

  5. Materials and Components Technology Division research summary, 1991

    Energy Technology Data Exchange (ETDEWEB)

    1991-04-01

    This division has the purpose of providing a R and D capability for design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs are in support of the Integral Fast Reactor, life extension for light water reactors, fuels development for the new production reactor and research and test reactors, fusion reactor first-wall and blanket technology, safe shipment of hazardous materials, fluid mechanics/materials/instrumentation for fossile energy systems, and energy conservation and renewables (including tribology, high- temperature superconductivity). Separate abstracts have been prepared for the data base.

  6. Research for enhancing reactor safety

    International Nuclear Information System (INIS)

    1989-05-01

    Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG) [de

  7. Energy and Environmental Systems Division 1981 research review

    International Nuclear Information System (INIS)

    1982-04-01

    To effectively manage the nation's energy and natural resources, government and industry leaders need accurate information regarding the performance and economics of advanced energy systems and the costs and benefits of public-sector initiatives. The Energy and Environmental Systems Division (EES) of Argonne National Laboratory conducts applied research and development programs that provide such information through systems analysis, geophysical field research, and engineering studies. During 1981, the division: analyzed the production economics of specific energy resources, such as biomass and tight sands gas; developed and transferred to industry economically efficient techniques for addressing energy-related resource management and environmental protection problems, such as the reclamation of strip-mined land; determined the engineering performance and cost of advanced energy-supply and pollution-control systems; analyzed future markets for district heating systems and other emerging energy technologies; determined, in strategic planning studies, the availability of resources needed for new energy technologies, such as the imported metals used in advanced electric-vehicle batteries; evaluated the effectiveness of strategies for reducing scarce-fuel consumption in the transportation sector; identified the costs and benefits of measures designed to stabilize the financial condition of US electric utilities; estimated the costs of nuclear reactor shutdowns and evaluated geologic conditions at potential sites for permanent underground storage of nuclear waste; evaluated the cost-effectiveness of environmental regulations, particularly those affecting coal combustion; and identified the environmental effects of energy technologies and transportation systems

  8. Report of Activity, 1996 - 1997. Vol. 1. Experimental Research Division

    International Nuclear Information System (INIS)

    Brunelle, Alain; Morlet, Marcel; Hutin, Christiane

    1999-01-01

    This report presents the activity of Experimental Research Division of the Orsay Institute of Nuclear Physics on 1996 - 1997. The following 10 sections are represented through summary reports or short communications: 1. Nuclear structure far from stability (with the topics: 1.1. Exotic nuclei -Secondary beams of radioactive ions; 1.2. On-line spectroscopy; 1.3. Discrete high-spin states); 2. High excitation energy nuclear states; 3. Nuclear matter and nucleus-nucleus collisions (which includes 3.1. Evolution of reaction mechanisms from 10 to 150 MeV/u; 3.2. Hot nuclei; 3.3. Ultra-relativistic collisions); 4. Hadronic physics (with the topics: 4.1 Meson production; 4.2. Spin modes in nuclei; 4.3. Hadronic physics with electromagnetic probes); 5. Radiochemistry (with the sub-divisions: 5.1. Studies related to radioactive waste management; 5.2. Optical spectroscopy of actinide and lanthanide ions in solid media); 6. Inter-disciplinary research (with the topics: 6.1. Heavy ion and cluster interactions with matter and surfaces; 6.2. Medical imaging); 8. Teaching; 9. Publications - Conferences - Seminars; 10 Internal reports - Lectures - Theses - Patents. The scientific staff of the following groups is also presented: 1. Group of Nuclear Structure by Reactions; 2. Group of Heavy Ion Nuclear Physics; 3. Intermediary Energy Group; 4. Hadron Physics Group; 5. Nuclei-Ions-Matter Group; 6. Radiochemistry Group; 7. Group of Exotic Deformed Nuclei; 8. Group of Physics-Biology Interface

  9. Division of Biological and Medical Research annual research summary, 1983

    Energy Technology Data Exchange (ETDEWEB)

    Barr, S.H. (ed.)

    1984-08-01

    This research summary contains brief descriptions of research in the following areas: (1) mechanisms of hepatocarcinogenesis; (2) role of metals in cocarcinogenesis and the use of liposomes for metal mobilization; (3) control of mutagenesis and cell differentiation in cultured cells by tumor promoters; (4) radiation effects in mammalian cells; (5) radiation carcinogenesis and radioprotectors; (6) life shortening, tumor induction, and tissue dose for fission-neutron and gamma-ray irradiations; (7) mammalian genetics and biostatistics; (8) radiation toxicity studies; (9) hematopoiesis in chronic toxicity; (10) molecular biology studies; (11) chemical toxicology; (12) carcinogen identification and metabolism; (13) metal metabolism and toxicity; and (14) neurobehavioral chronobiology. (ACR)

  10. Division of Biological and Medical Research annual research summary, 1983

    International Nuclear Information System (INIS)

    Barr, S.H.

    1984-08-01

    This research summary contains brief descriptions of research in the following areas: (1) mechanisms of hepatocarcinogenesis; (2) role of metals in cocarcinogenesis and the use of liposomes for metal mobilization; (3) control of mutagenesis and cell differentiation in cultured cells by tumor promoters; (4) radiation effects in mammalian cells; (5) radiation carcinogenesis and radioprotectors; (6) life shortening, tumor induction, and tissue dose for fission-neutron and gamma-ray irradiations; (7) mammalian genetics and biostatistics; (8) radiation toxicity studies; (9) hematopoiesis in chronic toxicity; (10) molecular biology studies; (11) chemical toxicology; (12) carcinogen identification and metabolism; (13) metal metabolism and toxicity; and (14) neurobehavioral chronobiology

  11. 59th Clinical Research Division Research Day Briefing

    Science.gov (United States)

    2016-10-27

    College of Lab Animal Medicine; Certified by American College of Veterinary Pathology 1 - PhD, Physiology/Biochem - Clinical Research Admin...Molecular Biology/Genomics - Next Generation Sequencing - Real Time PCR - Multi-Plex Assays Cell Biology - Flow Cytometry Microbiology Coagulation

  12. Safety administration division business report. The fourth quarter of 2001. Document on present state of affairs

    International Nuclear Information System (INIS)

    Kanamori, Masashi

    2002-06-01

    The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these businesses and utilizing the data concerning the businesses, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the fourth quarter news from January to March in 2002. (author)

  13. Safety administration division business report. The third quarter of 2001. Document on present state of affairs

    International Nuclear Information System (INIS)

    Kanamori, Masashi

    2002-04-01

    The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these business and utilizing the data concerning the business, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the third quarter news from October to December in 2001. (author)

  14. Chinese Road Safety and Driver Behavior Research

    OpenAIRE

    Wang, Junhua

    2015-01-01

    The seminar will begin with a brief overview of the Chinese road safety situation, including current safety problems, and then move on to discuss safety research including driver behavior, freeway operational safety, and infrastructure development.

  15. Technology Development, Evaluation, and Application (TDEA) FY 1999 Progress Report, Environment, Safety, and Health (ESH) Division

    Energy Technology Data Exchange (ETDEWEB)

    Larry G. Hoffman

    2000-12-01

    This progress report presents the results of 10 projects funded ($500K) in FY99 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Five are new projects for this year; seven projects have been completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published thirty-four papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space, were also provided to TDEA-funded projects by organizations external to ESH Division.

  16. Technology Development, Evaluation, and Application (TDEA) FY 1999 Progress Report, Environment, Safety, and Health (ESH) Division

    International Nuclear Information System (INIS)

    Hoffman, Larry G.

    2000-01-01

    This progress report presents the results of 10 projects funded ($500K) in FY99 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Five are new projects for this year; seven projects have been completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published thirty-four papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space, were also provided to TDEA-funded projects by organizations external to ESH Division

  17. Nuclear safety research in France

    International Nuclear Information System (INIS)

    Tanguy, P.

    1976-01-01

    As a consequence of the decision of choosing light water reactors (PWR) for the French nuclear plants of the next ten years, a large safety program has been launched referring to three physical barriers against fission product release: the fuel element cladding, main primary system boundary and the containment. The parallel development of French-designed fast breeder reactors involved safety studies on: sodium boiling, accidental fuel behavior, molten fuel-sodium interaction, core accident and protection, and external containment. The rapid development of nuclear energy resulted in a corresponding development of safety studies relating to nuclear fuel facilities. French regulations also required a special program to be developed for the realistic evaluation of the consequences of external agressions, the French cooperation to multinational safety research being also intensive

  18. Division of Biological and Medical Research annual technical report, 1981

    International Nuclear Information System (INIS)

    Rosenthal, M.W.

    1982-06-01

    This report summarizes research during 1981 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Low Level Radiation include comparison of lifetime effects in mice of low level neutron and gamma irradiation, delineation of the responses of dogs to continuous low level gamma irradiation, elucidation of mechanisms of radiation damage and repair in mammalian cells, and study of the genetic effects of high LET radiations. Carcinogenesis research addresses mechanisms of tumor initiation and promotion in rat liver, chemical carcinogenesis in cultured mammalian cells, and molecular and genetic mechanisms of chemical and ultraviolet mutagenesis in bacteria. Research in Toxicology uses a variety of cellular, whole animal, and chronobiological end points, chemical separations, and statistical models to evaluate the hazards and mechanisms of actions of metals, coal gasification by products, and other energy-related pollutants. Human Protein Index studies develop two-dimensional electrophoresis systems for diagnosis and detection of cancer and other disease. Biophysics research includes fundamental structural and biophysical investigations of immunoglobulins and key biological molecules using NMR, crystallographic, and x-ray and neutron small-angle scattering techniques. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies

  19. Division of Biological and Medical Research annual technical report, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.W. (ed.)

    1982-06-01

    This report summarizes research during 1981 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Low Level Radiation include comparison of lifetime effects in mice of low level neutron and gamma irradiation, delineation of the responses of dogs to continuous low level gamma irradiation, elucidation of mechanisms of radiation damage and repair in mammalian cells, and study of the genetic effects of high LET radiations. Carcinogenesis research addresses mechanisms of tumor initiation and promotion in rat liver, chemical carcinogenesis in cultured mammalian cells, and molecular and genetic mechanisms of chemical and ultraviolet mutagenesis in bacteria. Research in Toxicology uses a variety of cellular, whole animal, and chronobiological end points, chemical separations, and statistical models to evaluate the hazards and mechanisms of actions of metals, coal gasification by products, and other energy-related pollutants. Human Protein Index studies develop two-dimensional electrophoresis systems for diagnosis and detection of cancer and other disease. Biophysics research includes fundamental structural and biophysical investigations of immunoglobulins and key biological molecules using NMR, crystallographic, and x-ray and neutron small-angle scattering techniques. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies.

  20. AEC sets five year nuclear safety research program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The research by the government for the establishment of means of judging the adequacy of safety measures incorporated in nuclear facilities, including setting safety standards and collecting documents of general criteria, and the research by the industry on safety measures and the promotion of safety-related technique are stated in the five year program for 1976-80 reported by subcommittees, Atomic Energy Commission (AEC). Four considerations on the research items incorporated in the program are 1) technical programs relating to the safety of nuclear facilities and the necessary criteria, 2) priority of the relevant items decided according to their impact on circumstances, urgency, the defence-indepth concept and so on, 3) consideration of all relevant data and documents collected, and research subjects necessary to quantify safety measurement, and 4) consideration of technological actualization, the capability of each research body, the budget and the time schedule. In addition, seven major themes decided on the basis of these points are 1) reactivity-initiated accident, 2) LOCA, 3) fuel behavior, 4) structural safety, 5) radioactive release, 6) statistical method of safety evaluation, and 7) seismic characteristics. The committee has deliberated the appropriate division of researches between the government and the industry. A set of tables showing the nuclear safety research plan for 1976-80 are attached. (Iwakiri, K.)

  1. Division of Biological and Medical Research annual report 1978

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.W. (ed.)

    1978-01-01

    The research during 1978 in the Division of Biological and Medical Research, Argonne National Laboratory, is summarized. Studies related to nuclear energy include responses of beagles to continuous low-level /sup 60/Co gamma radiation, and development of leukemic indicators; comparison of lifetime effects in mice of low-level neutron and /sup 60/Co gamma radiation; genetic effects of high LET radiations; and metabolic and therapeutic studies of heavy metals. Studies of nonnuclear energy sources deal with characterization and toxicological evaluation of effluents of fluidized bed combustion and coal gasification; electrical storage systems; electric fields associated with energy transmission; and development of population projection models and assessment of human risk. Basic research studies include fundamental structural and biophysical investigations; circadian rhythms; mutagenesis in bacteria and mammalian cells; cell killing, damage, and repair in mammalian cells; carcinogenesis and cocarcinogenesis; the use of liposomes as biological carriers; and studies of environmental influences on life-span, physiological performance, and circadian cycles. In the area of medical development, proteins in urine and tissues of normal and diseased humans are analyzed, and advanced analytical procedures for use of stable isotopes in clinical research and diagnosis are developed and applied. The final sections of the report cover support facilities, educational activities, the seminar program, staff talks, and staff publications.

  2. Division of Biological and Medical Research annual technical report 1982

    International Nuclear Information System (INIS)

    Rosenthal, M.W.

    1983-05-01

    This report summarizes research during 1982 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Carcinogenesis address mechanisms of chemical and radiation carcinogenesis including the processes of tumor initiation and promotion. The studies employ rat liver and mouse skin models as well as human rodent cell culture systems. The use of liposomes for metal mobilization is also explored. Low Level Radiation studies include delineation of the hematopoietic and other responses of dogs to continuous low level gamma irradiation, comparison of lifetime effects in mice of low level neutron and gamma irradiation, and study of the genetic effects of high LET radiation. Molecular Biology research develops two-dimensional electrophoresis systems for diagnosis and detection of cancer and other diseases. Fundamental structural and biophysical investigations of immunoglobulins and other key proteins are included, as are studies of cell growth, and of molecular and cellular effects of solar uv light. Research in Toxicology uses cellular, physiological, whole animal, and chronobiological end points and chemical separations to elucidate mechanisms and evaluate hazards of coal conversion by-products, actinides, and toxic metals. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies

  3. Division of Biological and Medical Research annual report, 1980

    International Nuclear Information System (INIS)

    Rosenthal, M.W.

    1981-08-01

    The research during 1980 in the Division of Biological and Medical Research, Argonne National Laboratory, is summarized. Research related to nuclear energy includes the delineation, in the beagle, of the responses to continuous low level 60 Co gamma radiation and the development of cellular indicators of preclinical phases of leukemia; comparison of lifetime effects in mice of low level neutron and 60 Co gamma radiation; studies of the genetic effects of high LET radiations; and studies of the gastrointestinal absorption of the actinide elements. Research related to nonuclear energy sources deals with characterization and toxicological evaluation of process streams and effluents of coal gasification; with electrical storage systems; and electric fields associated with energy transmission. Proteins in human urine and selected tissues are examined by two-dimensional electrophoresis to detect disease and pollutant related changes. Assessment of human risk associated with nuclearing collective dose commitment will result in more attention being paid to potential releases of radionuclides at relatively short times after disposal

  4. Division of Biological and Medical Research annual technical report 1982

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.W. (ed.)

    1983-05-01

    This report summarizes research during 1982 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Carcinogenesis address mechanisms of chemical and radiation carcinogenesis including the processes of tumor initiation and promotion. The studies employ rat liver and mouse skin models as well as human rodent cell culture systems. The use of liposomes for metal mobilization is also explored. Low Level Radiation studies include delineation of the hematopoietic and other responses of dogs to continuous low level gamma irradiation, comparison of lifetime effects in mice of low level neutron and gamma irradiation, and study of the genetic effects of high LET radiation. Molecular Biology research develops two-dimensional electrophoresis systems for diagnosis and detection of cancer and other diseases. Fundamental structural and biophysical investigations of immunoglobulins and other key proteins are included, as are studies of cell growth, and of molecular and cellular effects of solar uv light. Research in Toxicology uses cellular, physiological, whole animal, and chronobiological end points and chemical separations to elucidate mechanisms and evaluate hazards of coal conversion by-products, actinides, and toxic metals. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies.

  5. Division of Biological and Medical Research annual report 1978

    International Nuclear Information System (INIS)

    Rosenthal, M.W.

    1978-01-01

    The research during 1978 in the Division of Biological and Medical Research, Argonne National Laboratory, is summarized. Studies related to nuclear energy include responses of beagles to continuous low-level 60 Co gamma radiation, and development of leukemic indicators; comparison of lifetime effects in mice of low-level neutron and 60 Co gamma radiation; genetic effects of high LET radiations; and metabolic and therapeutic studies of heavy metals. Studies of nonnuclear energy sources deal with characterization and toxicological evaluation of effluents of fluidized bed combustion and coal gasification; electrical storage systems; electric fields associated with energy transmission; and development of population projection models and assessment of human risk. Basic research studies include fundamental structural and biophysical investigations; circadian rhythms; mutagenesis in bacteria and mammalian cells; cell killing, damage, and repair in mammalian cells; carcinogenesis and cocarcinogenesis; the use of liposomes as biological carriers; and studies of environmental influences on life-span, physiological performance, and circadian cycles. In the area of medical development, proteins in urine and tissues of normal and diseased humans are analyzed, and advanced analytical procedures for use of stable isotopes in clinical research and diagnosis are developed and applied. The final sections of the report cover support facilities, educational activities, the seminar program, staff talks, and staff publications

  6. Progress of nuclear safety research. 2001

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-10-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

  7. Compilation of contract research for the Materials Engineering Branch, Division of Engineering: Annual report for FY 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators, nondestructive examination of primary components, and in safety research for decommissioning and decontamination, on-site storage and engineered safety features. The Materials Engineering Branch assembles abbreviated reports from all the branch contractors and publishes them in a single annual report as soon after the end of the year as possible so that the information developed throughout the year can be promptly used in the safety-regulatory process. This report, covering research conducted during Fiscal Year 1988 is the seventh volume of the series of NUREG-0975, ''Compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering.'' Individual projects are processed separately for the data bases

  8. Safety administration division business report. The first quarter of 2001. Business report

    International Nuclear Information System (INIS)

    Kanamori, Masashi

    2001-09-01

    As a consequence of this reorganization, the business of the Safety Administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, the business of the sanction concerning the Tokai Works, the protection of nuclear materials, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. In the respect of the purpose of summarizing these businesses and utilizing the data concerning the businesses, the report about a business achievement was determined to make. (author)

  9. Safety of Research Reactors. Specific Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This Safety Requirements publication establishes requirements for all main areas of safety for research reactors, with particular emphasis on requirements for design and operation. It explains the safety objectives and concepts that form the basis for safety and safety assessment for all stages in the lifetime of a research reactor. Technical and administrative requirements for the safety of new research reactors are established in accordance with these objectives and concepts, and they are to be applied to the extent practicable for existing research reactors. The safety requirements established in this publication for the management of safety and regulatory supervision apply to site evaluation, design, manufacturing, construction, commissioning, operation (including utilization and modification), and planning for decommissioning of research reactors (including critical assemblies and subcritical assemblies). The publication is intended for use by regulatory bodies and other organizations with responsibilities in these areas and in safety analysis, verification and review, and the provision of technical support.

  10. A digest of the Nuclear Safety Division report on the Fukushima Dai-ichi accident seminar (4). Issues identified by the accident

    International Nuclear Information System (INIS)

    Moriyama, Kumiaki; Abe, Kiyoharu

    2013-01-01

    AESJ Nuclear Safety Division published 'Report on the Fukushima Dai-ichi Accident Seminar - what was wrong and what should been down in future-' which would be published as five special articles of the AESJ journal. The Fukushima Dai-ichi accident identified issues of several activities directly related with nuclear safety in the areas of safety design, severe accident management and safety regulations. PRA, operational experiences and safety research could not always contribute safety assurance of nuclear power plant so much. This article (4) summarized technical issues based on related facts of the accident as much as possible and discussed' what was wrong and what should be down in future'. Important issues were identified from defense-in-depth philosophy and lessons learned on safety design were obtained from accident progression analysis. Activities against external events and continuous improvements of safety standards based on latest knowledge were most indispensable. Strong cooperation among experts in different areas was also needed. (T. Tanaka)

  11. 59th Medical Wing Clinical Research Division Clinical Investigations Program Pathology Poster

    Science.gov (United States)

    2017-04-28

    59 MDW/SGVU SUBJECT: Professional Presentation Approval 1. Your paper, entitled 59th Medical Wing Clinical Research Division Clinical Investigations...Program Pathology Poster presented at/published to For hanging in a hallway of the 591h Medical Wing Clinical Research Division, Bldg 4430 in...Graduate Health Sciences Education student and your department has told you they cannot fund your publication, the 59th Clinical Research Division may

  12. Health Physics Division annual report for the period ending December 31, 1972 Part I : Research and development

    International Nuclear Information System (INIS)

    1973-01-01

    The Health Physics Division of the Bhabha Atomic Research Centre, Bombay (India) is responsible for: (i) assessment and control of radiation and industrial hazards in various research establishments and industrial installations of the Department of Atomic Energy and (ii) prescribing limits and conditions in respect of waste releases to the environment from the above establishments and installations. For effective discharge of these responsibilities, the Division is engaged in various research programmes in the following areas: (1) radiation dosimetry (2) instrumentation (3) pollution (4) environmental radioactivity, both natural and artificial (5) radioactive contamination and nuclear safety (6) industrial hygiene and safety (7) radioecology (8) micrometeorology. These programmes are described in brief. (M.G.B.)

  13. About the Western Ecology Division (WED) of EPA's National Health and Environmental Effects Research Laboratory

    Science.gov (United States)

    The Western Ecology Division (WED) conducts innovative research on watershed ecological epidemiology and the development of tools to achieve sustainable and resilient watersheds for application by stakeholders.

  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. Radiation safety research information database

    International Nuclear Information System (INIS)

    Yukawa, Masae; Miyamoto, Kiriko; Takeda, Hiroshi; Kuroda, Noriko; Yamamoto, Kazuhiko

    2004-01-01

    National Institute of Radiological Sciences in Japan began to construct Radiation Safety Research Information Database' in 2001. The research information database is of great service to evaluate the effects of radiation on people by estimating exposure dose by determining radiation and radioactive matters in the environment. The above database (DB) consists of seven DB such as Nirs Air Borne Dust Survey DB, Nirs Environmental Tritium Survey DB, Nirs Environmental Carbon Survey DB, Environmental Radiation Levels, Abe, Metabolic Database for Assessment of Internal Dose, Graphs of Predicted Monitoring Data, and Nirs nuclear installation environment water tritium survey DB. Outline of DB and each DB are explained. (S.Y.)

  16. Power reactor core safety research

    International Nuclear Information System (INIS)

    Rim, C.S.; Kim, W.C.; Shon, D.S.; Kim, J.

    1981-01-01

    As a part of nuclear safety research program, a project was launched to develop a model to predict fuel failure, to produce the data required for the localizaton of fuel design and fabrication technology, to establish safety limits for regulation of nuclear power plants and to develop reactor operation method to minimize fuel failure through the study of fuel failure mechanisms. During 1980, the first year of this project, various fuel failure mechanisms were analyzed, an experimental method for out-of-pile tests to study the stress corrosion cracking (SCC) behaviour of Zircaloy cladding underiodine environment was established, and characteristics of PWR and CANDU Zircaloy specimens were examined. Also developed during 1980 were the methods and correlations to evaluate fuel failures in the reactor core based on operating data from power reactors

  17. Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

    International Nuclear Information System (INIS)

    1994-09-01

    Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA's Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project

  18. Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA`s Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project.

  19. Accelerator and Fusion Research Division: 1984 summary of activities

    International Nuclear Information System (INIS)

    1985-05-01

    During fiscal 1984, major programmatic activities in AFRD continued in each of five areas: accelerator operations, highlighted by the work of nuclear science users, who produced clear evidence for the formation of compressed nuclear matter during heavy-ion collisions; high-energy physics, increasingly dominated by our participation in the design of the Superconducting Super Collider; heavy-ion fusion accelerator research, which focused on the design of a four-beam experiment as a first step toward assessing the promise of heavy-ion inertial-confinement fusion; and research at the Center for X-Ray Optics, which completed its first year of broadly based activities aimed at the exploitation of x-ray and ultraviolet radiation. At the same time, exploratory studies were under way, aimed at investigating major new programs for the division. During the past year, for example, we took a preliminary look at how we could use the Bevatron as an injector for a pair of colliding-beam rings that might provide the first glimpse of a hitherto unobserved state of matter called the quark-gluon plasma. Together with Livermore scientists, we also conducted pioneering high-gain free-electron laser (FEL) experiments and proposed a new FEL-based scheme (called the two-beam accelerator) for accelerating electrons to very high energies. And we began work on the design of the Coherent XUV Facility (CXF), an advanced electron storage ring for the production of intense coherent radiation from either undulators or free-electron lasers

  20. Trends in fuel reprocessing safety research

    International Nuclear Information System (INIS)

    Tsujino, Takeshi

    1981-01-01

    With the operation of a fuel reprocessing plant in the Power Reactor and Nuclear Fuel Development Corporation (PNC) and the plan for a second fuel reprocessing plant, the research on fuel reprocessing safety, along with the reprocessing technology itself, has become increasingly important. As compared with the case of LWR power plants, the safety research in this field still lags behind. In the safety of fuel reprocessing, there are the aspects of keeping radiation exposure as low as possible in both personnel and local people, the high reliability of the plant operation and the securing of public safety in accidents. Safety research is then required to establish the safety standards and to raise the rate of plant operation associated with safety. The following matters are described: basic ideas for the safety design, safety features in fuel reprocessing, safety guideline and standards, and safety research for fuel reprocessing. (J.P.N.)

  1. Technology Development, Evaluation, and Application (TDEA) FY 1998 Progress Report Environment, Safety, and Health (ESH) Division

    Energy Technology Data Exchange (ETDEWEB)

    Larry G. Hoffman; Kenneth Alvar; Thomas Buhl; Bruce Erdal; Philip Fresquez; Elizabeth Foltyn; Wayne Hansen; Bruce Reinert

    1999-06-01

    This progress report presents the results of 10 projects funded ($504K) in FY98 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Nine projects are new for this year; two projects were completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published 19 papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space were also provided to the TDEA-funded projects by organizations external to ESH Division. Products generated from the projects funded in FY98 included a new extremity dosimeter that replaced the previously used finger-ring dosimeters, a light and easy-to-use detector to measure energy deposited by neutron interactions, and a device that will allow workers to determine the severity of a hazard.

  2. Environment and safety research status report: 1993

    International Nuclear Information System (INIS)

    1993-03-01

    The 1993 status report discusses ongoing and planned research activities in the GRI Environment and Safety Program. The objectives and goals, accomplishments, and strategy along with the basis for each project area are presented for the supply, end use, and gas operations subprograms. Within the context of these subprograms, contract status summaries under their conceptual titles are given for the following project areas: Gas Supply Environmental and Safety Research, Air Quality Research, End Use Equipment Safety Research, Gas Operations Safety Research, Liquefied Natural Gas, Safety Research, and Gas Operations Environmental Research

  3. High Energy Physics division semiannual report of research activities, January 1, 1998 - June 30, 1998

    International Nuclear Information System (INIS)

    Norem, J.; Rezmer, R.; Schuur, C.; Wagner, R.

    1999-01-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1998 through June 30, 1998. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of Division publications and colloquia are included

  4. High Energy Physics Division semiannual report of research activities, January 1, 1996--June 30, 1996

    International Nuclear Information System (INIS)

    Norem, J.; Rezmer, R.; Wagner, R.

    1997-07-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1 - June 30, 1996. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. List of Division publications and colloquia are included

  5. High Energy Physics Division semiannual report of research activities, January 1, 1992--June 30, 1992

    International Nuclear Information System (INIS)

    Schoessow, P.; Moonier, P.; Talaga, R.; Wagner, R.

    1992-11-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1992--June 30, 1992. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  6. High Energy Physics Division semiannual report of research activities, January 1, 1994--June 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1994-June 30, 1994. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included.

  7. High Energy Physics Division. Semiannual report of research activities, January 1, 1995--June 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, R.; Schoessow, P.; Talaga, R.

    1995-12-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1995-July 31, 1995. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included.

  8. High Energy Physics Division semiannual report of research activities, July 1, 1991--December 31, 1991

    International Nuclear Information System (INIS)

    Schoessow, P.; Moonier, P.; Talaga, R.; Wagner, R.

    1992-04-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of July 1, 1991--December 31, 1991. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  9. High Energy Physics Division. Semiannual report of research activities, January 1, 1995--June 30, 1995

    International Nuclear Information System (INIS)

    Wagner, R.; Schoessow, P.; Talaga, R.

    1995-12-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1995-July 31, 1995. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  10. High Energy Physics Division semiannual report of research activities July 1, 1997 - December 31, 1997

    International Nuclear Information System (INIS)

    Norem, J.; Rezmer, R.; Schuur, C.; Wagner, R.

    1998-01-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period July 1, 1997--December 31, 1997. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of Division publications and colloquia are included

  11. High Energy Physics Division semiannual report of research activities, July 1, 1992--December 30, 1992

    International Nuclear Information System (INIS)

    Schoessow, P.; Moonier, P.; Talaga, R.; Wagner, R.

    1993-07-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of July 1, 1992--December 30, 1992. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  12. High Energy Physics Division semiannual report of research activities, July 1, 1993--December 31, 1993

    International Nuclear Information System (INIS)

    Wagner, R.; Moonier, P.; Schoessow, P.; Talaga, R.

    1994-05-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of July 1, 1993--December 31, 1993. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  13. High Energy Physics Division semiannual report of research activities, January 1, 1994--June 30, 1994

    International Nuclear Information System (INIS)

    1994-09-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1994-June 30, 1994. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  14. High Energy Physics Division semiannual report of research activities, January 1, 1993--June 30, 1993

    International Nuclear Information System (INIS)

    Schoessow, P.; Moonier, P.; Talaga, R.; Wagner, R.

    1993-12-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1993--June 30, 1993. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  15. High Energy Physics Division semiannual report of research activities, July 1, 1994--December 31, 1994

    International Nuclear Information System (INIS)

    Wagner, R.; Schoessow, P.; Talaga, R.

    1995-04-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of July 1, 1994--December 31, 1994. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  16. High Energy Physics division semiannual report of research activities, January 1, 1998--June 30, 1998.

    Energy Technology Data Exchange (ETDEWEB)

    Ayres, D. S.; Berger, E. L.; Blair, R.; Bodwin, G. T.; Drake, G.; Goodman, M. C.; Guarino, V.; Klasen, M.; Lagae, J.-F.; Magill, S.; May, E. N.; Nodulman, L.; Norem, J.; Petrelli, A.; Proudfoot, J.; Repond, J.; Schoessow, P. V.; Sinclair, D. K.; Spinka, H. M.; Stanek, R.; Underwood, D.; Wagner, R.; White, A. R.; Yokosawa, A.; Zachos, C.

    1999-03-09

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1998 through June 30, 1998. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of Division publications and colloquia are included.

  17. Safety Research and Experimental Coal Mines

    Data.gov (United States)

    Federal Laboratory Consortium — Safety Research and Experimental Coal MinesLocation: Pittsburgh SiteThe Safety Research Coal Mine and Experimental Mine complex is a multi-purpose underground mine...

  18. Analysis of the survey results for the safety culture attitudes of HANARO management division staff

    Energy Technology Data Exchange (ETDEWEB)

    Lee, M.; Hwang, S. Y.; Lim, I. C.; Kang, T. J.; Choi, H. Y

    2003-12-01

    This report provides the that analysis results of the surveys on the safety culture attitude and related topics for the HANARO Management Division staff. The survey form consisted of the questionnaire on the safety culture attitude, happiness and life style, drinking habit and traffic safety attitude. The key information drawn from the analysis are as follow; First, the level of safety culture attitude of the staff was confirmed and it was found that the attitude improved when the present analysis results were compared with them for the survey in 1998. Second, the degree of happiness that the staff feel is higher than the average Korean and they enjoy more leisure time than the average Korean. Third, the staff drink more alcohol than the average Korean. Thus, the drinking habit must be improved for the health of the staff. Fourth, the questionnaire of the happiness and the traffic safety attitude should be improved to verify the hypotheses on the relation between them and the safety culture attitude.

  19. Analysis of the survey results for the safety culture attitudes of HANARO management division staff

    International Nuclear Information System (INIS)

    Lee, M.; Hwang, S. Y.; Lim, I. C.; Kang, T. J.; Choi, H. Y.

    2003-12-01

    This report provides the that analysis results of the surveys on the safety culture attitude and related topics for the HANARO Management Division staff. The survey form consisted of the questionnaire on the safety culture attitude, happiness and life style, drinking habit and traffic safety attitude. The key information drawn from the analysis are as follow; First, the level of safety culture attitude of the staff was confirmed and it was found that the attitude improved when the present analysis results were compared with them for the survey in 1998. Second, the degree of happiness that the staff feel is higher than the average Korean and they enjoy more leisure time than the average Korean. Third, the staff drink more alcohol than the average Korean. Thus, the drinking habit must be improved for the health of the staff. Fourth, the questionnaire of the happiness and the traffic safety attitude should be improved to verify the hypotheses on the relation between them and the safety culture attitude

  20. Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology. Annual report for FY 1985. Volume 4

    International Nuclear Information System (INIS)

    1986-03-01

    The compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research, concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators and for non-destructive examination of primary system components. This report, covering research conducted during Fiscal Year 1985, is the fourth volume of the series of NUREG-0975, Compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering Technology

  1. Compilation of contract research for the Materials Engineering Branch, Division of Engineering Technology. Annual report for FY 1984. Volume 3

    International Nuclear Information System (INIS)

    1985-04-01

    This compilation of annual reports by contractors to the Materials Engineering Branch of the NRC Office of Research, concentrates on achievments in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators and for non-destructive examination of primary system components. This report, covering research conducted during Fiscal Year 1984, is the third volume of the series of NUREG-0975, compilation of Contractor Research for the Materials Engineering Branch, Division of Engineering Technology

  2. High Energy Physics Division semiannual report of research activities, July 1, 1990--December 31, 1990

    International Nuclear Information System (INIS)

    Berger, E.; Moonier, P.; May, E.; Norem, J.

    1991-02-01

    A report is presented of research and development activities conducted in the High Energy Physics Division at Argonne National Laboratory during the six month period July 1 through December 31, 1990. Analyses of data from experiments performed by members of the Division are summarized, and the status of experiments taking data and of those being prepared is reviewed. Descriptions are included of research on theoretical and phenomenological topics in particle physics. Progress reports are provided on accelerator research and development, detector research and development, and experimental facilities research. Lists are presented of publications, of colloquia and conference talks, and of significant external community activities of members of the Division

  3. Reactor safety research and safety technology. Pt. 2

    International Nuclear Information System (INIS)

    Theenhaus, R.; Wolters, J.

    1987-01-01

    The state of HTR safety research work reached permits a comprehensive and reliable answer to be given to questions which have been raised by the reactor accident at Chernobyl, regarding HTR safety. Together with the probability safety analyses, the way to a safety concept suitable for an HTR is cleared; instructions are given for design optimisation with regard to safety technique and economy. The consequences of a graphite fire, the neutron physics design and the consequenes of the lack of a safety containment are briefly described. (DG) [de

  4. Division of Biological and Medical Research annual report, 1979

    International Nuclear Information System (INIS)

    Rosenthal, M.W.

    1979-01-01

    Separate abstracts were prepared for 14 of the 20 sections included in this progress report. The other 6 sections include: introductory statements by the division director; descriptions of the animal, computer, electron microscope, and radiation support facilities; a listing of the educational activities, divisional seminars, and oral presentations by staff members; and divisional staff publications. An author index to the report is included

  5. Progress of nuclear safety research-2004

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

    2005-03-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

  6. Safety research plan, JFY 2013 edition

    International Nuclear Information System (INIS)

    2013-09-01

    As for the regulatory issues the governments or JNES considered necessary, JNES had updated every year '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 plan, JFY 2013 Edition' was compiled aiming at promotion of appropriate reflection and flexible application of research achievements for tacking the regulatory issues taking account of importance and urgency dependent on trend of nuclear safety regulations as well as collective management of safety research and safety survey. 5 new research projects were established with 4 unified research projects and 6 terminated research projects. Finally modified safety research areas, subjects and research projects, JFY 2013 Edition were as follows: design review of nuclear power plant (7 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (one subject having 4 research projects), 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 5), 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). Safety reviews consisted of 6 projects in 3 areas extracting the regulatory issues. As for urgent research projects on the basis of the disaster at Fukushima Daiichi NPP accident, 7 research projects in 4 urgent subjects were as follows: examination for new safety regulation (4 research projects generalized in the above research projects), development of newly necessary evaluation methods (one research project generalized in the above research project), evaluation of the validity for the work for convergence at Fukushima

  7. Reactor safety research in Sweden

    International Nuclear Information System (INIS)

    Pershagen, B.

    1980-02-01

    Objectives, means and results of Swedish light water reactor safety research during the 1970s are reviewed. The expenditure is about 40 Million Swkr per year excluding industry. Large efforts have been devoted to experimental studies of loss of coolant accidents. Large scale containment response tests for simulated pipe breaks were carried out at the Marviken facility. At Studsvik a method for testing fuel during fast power changes has been developed. Stress corrosion, crack growth and the effect of irradiation on the strength ductility of Zircaloy tube was studied. A method for determining the fracture toughness of pressure vessel steel was developed and it was shown that the fracture toughness was lower than earlier assumed. The release of fission products to reactor water was studied and so was the release, transport and removal of airborne radioactive matter for Swedish BWRs and PWRs. Test methods for iodine filter systems were developed. A system for continuous monitoring of radioactive noble gas stack release was developed for the Ringhals plant. Attention was drawn to the importance of the human factor for reactor safety. Probabilistic methods for risk analysis were applied to the Barsebaeck 2 and Forsmark 3 boiling water reactors. Procedures and working conditions for operator personnel were investigated. (GBn)

  8. The safety and pharmacokinetics of single-agent and combination therapy with megestrol acetate and dronabinol for the treatment of HIV wasting syndrome. The DATRI 004 Study Group. Division of AIDS Treatment Research Initiative.

    Science.gov (United States)

    Timpone, J G; Wright, D J; Li, N; Egorin, M J; Enama, M E; Mayers, J; Galetto, G

    1997-03-01

    This randomized, open-labeled, multicenter study was designed to assess safety and pharmacokinetics of dronabinol (Marinol) tablets and megestrol acetate (Megace) micronized tablets, alone and in combination, for treatment of HIV wasting syndrome. Weight and quality of life data were also collected. Fifty-two patients (mean CD4+ count, 59 cells/microliter) were randomized to one of four treatment arms: dronabinol 2.5 mg twice/day (D); megestrol acetate 750 mg/day (M750); megestrol acetate 750 mg/day+dronabinol 2.5 mg twice/day (M750+D); or megestrol acetate 250 mg/day+dronabinol 2.5 mg twice/day (M250+D). After therapy initiation, 47 patients returned for at least one visit, and 39 completed the planned 12 weeks of study visits. Occurrence of adverse events, drug discontinuation, new AIDS-defining conditions, or CD4+ T lymphocyte changes were not statistically significantly different among arms. Serious adverse events assessed as related to dronabinol included CNS events (e.g., confusion, anxiety, emotional lability, euphoria, hallucinations) and those assessed as related to megestrol acetate included dyspnea, liver enzyme changes, and hyperglycemia. The mean weight change +/- SE over 12 weeks was as follows: D, -2.0 +/- 1.3 kg; M750, +6.5 +/- 1.1 kg; M750+D, +6.0 +/- 1.0 kg; and M250+D, -0.3 +/- 1.0 kg (difference among treatment arms, p = 0.0001). Pharmacokinetic parameters measured after 2 weeks of therapy for M750 were Cmax = 985 ng/ml and AUC = 22,487 ng x hr/ml, and for dronabinol and its active metabolite (HO-THC), respectively, were Cmax = 2.01; 4.61 ng/ml and AUC = 5.3; 23.7 ng x hr/ml. For megestrol acetate, but not dronabinol, there was a positive correlation at week 2 between both Cmax and AUC with each of the following: (1) weight change, (2) breakfast visual analog scale for hunger (VASH) score, and (3) dinner VASH score.

  9. Report to NASA Committee on Aircraft Operating Problems Relative to Aviation Safety Engineering and Research Activities

    Science.gov (United States)

    1963-01-01

    The following report highlights some of the work accomplished by the Aviation Safety Engineering and Research Division of the Flight Safety Foundations since the last report to the NASA Committee on Aircraft Operating Problems on 22 May 1963. The information presented is in summary form. Additional details may be provided upon request of the reports themselves may be obtained from AvSER.

  10. Safety research for CANDU reactors

    International Nuclear Information System (INIS)

    Hancox, W.T.

    1982-10-01

    Continuing research to develop and verify computer models of CANDU-PHW reactor process and safety systems is described. It is focussed on loss-of-coolant accidents (LOCAs) because they are the precursors of more serious accidents. Research topics include: (i) fluid-dynamic and heat-transfer processes in the heat transport system during the blowdown and refilling phases of LOCAs; (ii) thermal and mechanical behaviour of fuel elements; (iii) thermal and mechanical behaviour of the fuel and the fuel-channel assembly in situations where the heavy-water moderator is the sink for decay heat produced in the fuel; (iv) chemical behaviour of fission gases that might be released into the reactor coolant and transported to the containment system; and (v) combustion of hydrogen-air-steam mixtures that would be produced if fuel temperatures were sufficiently high to initiate the zirconium-water reaction. The current status of the research on each of these topics is highlighted with particular emphasis on the conclusions reached to date and their impact on the continuing program

  11. Risk as a target of safety research

    International Nuclear Information System (INIS)

    Krueger, W.

    1986-01-01

    Job creation is not the idea behind the demand for risk studies to be intensified in safety research. Risks are not only a target safety research should investigate, they are a subject that actually can be most adequately investigated by safety research. Assuming a neutral position between irrational fears and interest-minded problem minimization, that is the central approach and the ethics of a safety scientist. The Babylonian confusion of terminology experienced after the Chernobyl accident is a good example proving the necessity of fostering the neutral professionalism in safety research. (orig./DG) [de

  12. 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

  13. Recent innovations in IFR safety research

    International Nuclear Information System (INIS)

    Wade, D.C.

    1994-01-01

    Recent progress in IFR safety research suggests potential for two extensions of passive features to improve the robustness of safety response. This report provides a discussion of these recent innovations

  14. IAEA safety standards for research reactors

    International Nuclear Information System (INIS)

    Abou Yehia, H.

    2007-01-01

    The general structure of the IAEA Safety Standards and the process for their development and revision are briefly presented and discussed together with the progress achieved in the development of Safety Standards for research reactor. These documents provide the safety requirements and the key technical recommendations to achieve enhanced safety. They are intended for use by all organizations involved in safety of research reactors and developed in a way that allows them to be incorporated into national laws and regulations. The author reviews the safety standards for research reactors and details their specificities. There are 4 published safety standards: 1) Safety assessment of research reactors and preparation of the safety analysis report (35-G1), 2) Safety in the utilization and modification of research reactors (35-G2), 3) Commissioning of research reactors (NS-G-4.1), and 4) Maintenance, periodic testing and inspection of research reactors (NS-G-4.2). There 5 draft safety standards: 1) Operational limits and conditions and operating procedures for research reactors (DS261), 2) The operating organization and the recruitment, training and qualification of personnel for research reactors (DS325), 3) Radiation protection and radioactive waste management in the design and operation of research reactors (DS340), 4) Core management and fuel handling at research reactors (DS350), and 5) Grading the application of safety requirements for research reactors (DS351). There are 2 planned safety standards, one concerning the ageing management for research reactor and the second deals with the control and instrumentation of research reactors

  15. Activities on safety for the cross-cutting issue of research reactors in the IAEA

    International Nuclear Information System (INIS)

    Perrotta, J.A.; Boado Magan, H.J.

    2003-01-01

    IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety and implemented by the Engineering Safety Section through its Research Reactor Safety Unit. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities are discussed in this paper: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOCs); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the (Integrated Safety Assessment of Research Reactors) INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors developed, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors conducted in the year 2002 and the results obtained. (author)

  16. Status of nuclear safety research - 2000

    International Nuclear Information System (INIS)

    Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

    2000-11-01

    The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

  17. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

  18. Division of Biological and Medical Research research summary 1984-1985

    Energy Technology Data Exchange (ETDEWEB)

    Barr, S.H. (ed.)

    1985-08-01

    The Division of Biological and Medical Research at Argonne National Laboratory conducts multidisciplinary research aimed at defining the biological and medical hazards to man from energy technologies and new energy options. These technically oriented studies have a strong base in fundamental research in a variety of scientific disciplines, including molecular and cellular biology, biophysics, genetics, radiobiology, pharmacology, biochemistry, chemistry, environmental toxicology, and epidemiology. This research summary is organized into six parts. The first five parts reflect the Divisional structure and contain the scientific program chapters, which summarize the activities of the individual groups during the calendar year 1984 and the first half of 1985. To provide better continuity and perspective, previous work is sometimes briefly described. Although the summaries are short, efforts have been made to indicate the range of research activities for each group.

  19. Division of Biological and Medical Research research summary 1984-1985

    International Nuclear Information System (INIS)

    Barr, S.H.

    1985-08-01

    The Division of Biological and Medical Research at Argonne National Laboratory conducts multidisciplinary research aimed at defining the biological and medical hazards to man from energy technologies and new energy options. These technically oriented studies have a strong base in fundamental research in a variety of scientific disciplines, including molecular and cellular biology, biophysics, genetics, radiobiology, pharmacology, biochemistry, chemistry, environmental toxicology, and epidemiology. This research summary is organized into six parts. The first five parts reflect the Divisional structure and contain the scientific program chapters, which summarize the activities of the individual groups during the calendar year 1984 and the first half of 1985. To provide better continuity and perspective, previous work is sometimes briefly described. Although the summaries are short, efforts have been made to indicate the range of research activities for each group

  20. High Energy Physics Division semiannual report of research activities, July 1, 1996 - December 31, 1996

    International Nuclear Information System (INIS)

    Norem, J.; Rezmer, R.; Wagner, R.

    1997-12-01

    This report is divided into the following areas: (1) experimental research program; (2) theoretical research program; (3) accelerator research and development; (4) divisional computing activities; (5) publications; (6) colloquia and conference talks; (7) high energy physics community activities; and (7) High Energy Physics Division research personnel. Summaries are given for individual research programs for activities (1), (2) and (3)

  1. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  2. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    International Nuclear Information System (INIS)

    2013-01-01

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  3. IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Alcala, F.; Di Meglio, A.F.

    1995-01-01

    This paper describes the IAEA programme on research reactor safety and includes the safety related areas of conversions to the use of low enriched uranium (LEU) fuel. The program is based on the IAEA statutory responsibilities as they apply to the requirements of over 320 research reactors operating around the world. The programme covers four major areas: (a) the development of safety documents; (b) safety missions to research reactor facilities; (c) support of research programmes on research reactor safety; (d) support of Technical Cooperation projects on research reactor safety issues. The demand for these activities by the IAEA member states has increased substantially in recent years especially in developing countries with increasing emphasis being placed on LEU conversion matters. In response to this demand, the IAEA has undertaken an extensive programme for each of the four areas above. (author)

  4. Overview of NASA Glenn Research Center's Communications and Intelligent Systems Division

    Science.gov (United States)

    Miranda, Felix A.

    2016-01-01

    The Communications and Intelligent Systems Division provides expertise, plans, conducts and directs research and engineering development in the competency fields of advanced communications and intelligent systems technologies for application in current and future aeronautics and space systems.

  5. About the Atlantic Ecology Division (AED) of EPA's National Health and Environmental Effects Research Laboratory

    Science.gov (United States)

    The Atlantic Ecology Division (AED), conducts innovative research and predictive modeling to assess and forecast the risks of anthropogenic stressors to near coastal waters and their watersheds, to develop tools to support resilient watersheds.

  6. Accelerator and Fusion Research Division. Annual report, October 1977--September 1978

    Energy Technology Data Exchange (ETDEWEB)

    1979-04-01

    Research is reported for the combined groups consisting of the Accelerator Division and the Magnetic Fusion Energy Group. Major topics reported include accelerator operations, magnetic fusion energy, and advanced accelerator development. (GHT)

  7. Safety at Work : Research Methodology

    NARCIS (Netherlands)

    Beurden, van K. (Karin); Boer, de J. (Johannes); Brinks, G. (Ger); Goering-Zaburnenko, T. (Tatiana); Houten, van Y. (Ynze); Teeuw, W. (Wouter)

    2012-01-01

    In this document, we provide the methodological background for the Safety atWork project. This document combines several project deliverables as defined inthe overall project plan: validation techniques and methods (D5.1.1), performanceindicators for safety at work (D5.1.2), personal protection

  8. USNRC HTGR safety research program overview

    International Nuclear Information System (INIS)

    Foulds, R.B.

    1982-01-01

    An overview is given of current activities and planned research efforts of the US Nuclear Regulatory Commission (NRC) HTGR Safety Program. On-going research at Brookhaven National Laboratory, Oak Ridge National Laboratory, Los Alamos National Laboratory, and Pacific Northwest Laboratory are outlined. Tables include: HTGR Safety Issues, Program Tasks, HTGR Computer Code Library, and Milestones for Long Range Research Plan

  9. Spanish Nuclear Safety Research under International Frameworks

    Energy Technology Data Exchange (ETDEWEB)

    Herranz, L. E.; Reventos, F.; Ahnert, C.; Jimenez, G.; Queral, C.; Verdu, G.; Miro, R.; Gallardo, S.

    2013-10-01

    The Nuclear Safety research requires a wide international collaboration of several involved groups. In this sense this paper pretends to show several examples of the Nuclear Safety research under international frameworks that is being performed in different Universities and Research Institutions like CIEMAT, Universitat Politecnica de Catalunya (UPC), Universidad Politecnica de Madrid (UPM) and Universitat Politenica de Valencia (UPV). (Author)

  10. 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...

  11. 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...

  12. Research and development activities of High Pressure Physics Division (October 1993 - March 1996)

    Energy Technology Data Exchange (ETDEWEB)

    Gyanchandani, Jyoti; Gangrade, B K [eds.; High Pressure Physics Div., Bhabha Atomic Research Centre, Mumbai (India)

    1996-07-01

    The research and development activities of the High Pressure Physics Division during the period October 1993-March 1996 are reported in the form of collection of papers presented in journals, conference proceedings and abstracts in conferences and Bhabha Atomic Research Centre (BARC) technical reports. The report is organised in two sections: (A) High Pressure Physics Division, and (B) Seismology Section. A list of staff members is enclosed at the end.

  13. Research and development activities of High Pressure Physics Division (October 1993 - March 1996)

    International Nuclear Information System (INIS)

    Gyanchandani, Jyoti; Gangrade, B.K.

    1996-07-01

    The research and development activities of the High Pressure Physics Division during the period October 1993-March 1996 are reported in the form of collection of papers presented in journals, conference proceedings and abstracts in conferences and Bhabha Atomic Research Centre (BARC) technical reports. The report is organised in two sections: (A) High Pressure Physics Division, and (B) Seismology Section. A list of staff members is enclosed at the end

  14. Progress of nuclear safety research - 2005

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amaya, Masaki; Saito, Junichi; Sato, Atsushi; Sono, Hiroki; Tamaki, Hitoshi; Tonoike, Kotaro; Nemoto, Yoshiyuki; Motoki, Yasuo; Moriyama, Kiyofumi; Yamaguchi, Tetsuji; Araya, Fumimasa

    2006-03-01

    The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities. (author)

  15. Progress of nuclear safety research. 2003

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amagai, Masaki; Tobita, Tohru

    2004-03-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001, and the integrity evaluation of cracked core shroud of BWRs of the Tokyo Electric Power Company performed for assistance to the Nuclear Safety Commission in reviewing the evaluation reports by the licensees. (author)

  16. A research on the enhancement of research management efficiency for the division of research, Korea cancer center hospital

    International Nuclear Information System (INIS)

    Lee, S. W.; Ma, K. H.; Kim, J. R.; Lee, D. C.; Lee, J. H.

    1999-06-01

    The research activities of Korea Cancer Center Hospital have increased for the past a few years just in proportion to the increase of research budget, but the assisting manpower of the office of research management has never been increased and the indications are that the internal and external circumstances will not allow the recruitment for a fairly long time. It has, therefore, become inevitable to enhance the work efficiency of the office by analyzing the administrative research assistance system, finding out problems and inefficiency factors, and suggesting possible answers to them. The office of research management and international cooperation has conducted this research to suggest possible ways to facilitate the administrative support for the research activities of Korea Cancer Center Hospital By analyzing the change of research budget, organization of the division of research and administrative support, manpower, and the administrative research supporting system of other institutes, we suggested possible ways to enhance the work efficiency for administrative research support and developed a relative database program. The research report will serve as a data for the organization of research support division when the Radiation Medicine Research Center is established. The database program has already been used for research budget management

  17. RB research reactor safety report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document

  18. Materials and Molecular Research Division annual report, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    Research is presented concerning materials science including metallurgy and ceramics; solid state physics; and materials chemistry; chemical sciences covering radiation science, chemical physics, and chemical energy; nuclear science; coal research; solar energy; magnetic fusion, conservation; and environmental research. (FS)

  19. Researchers' Roles in Patient Safety Improvement.

    Science.gov (United States)

    Pietikäinen, Elina; Reiman, Teemu; Heikkilä, Jouko; Macchi, Luigi

    2016-03-01

    In this article, we explore how researchers can contribute to patient safety improvement. We aim to expand the instrumental role researchers have often occupied in relation to patient safety improvement. We reflect on our own improvement model and experiences as patient safety researchers in an ongoing Finnish multi-actor innovation project through self-reflective narration. Our own patient safety improvement model can be described as systemic. Based on the purpose of the innovation project, our improvement model, and the improvement models of the other actors in the project, we have carried out a wide range of activities. Our activities can be summarized in 8 overlapping patient safety improvement roles: modeler, influencer, supplier, producer, ideator, reflector, facilitator, and negotiator. When working side by side with "practice," researchers are offered and engage in several different activities. The way researchers contribute to patient safety improvement and balance between different roles depends on the purpose of the study, as well as on the underlying patient safety improvement models. Different patient safety research paradigms seem to emphasize different improvement roles, and thus, they also face different challenges. Open reflection on the underlying improvement models and roles can help researchers with different backgrounds-as well as other actors involved in patient safety improvement-in structuring their work and collaborating productively.

  20. Accomplishments and needs in safety research

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1988-01-01

    My purpose today is to review recent accomplishments in water reactor safety research and to point out important tasks that remain to be done. I will also comment on the changes of focus that I see ahead in reactor safety research. I speak from a U.S. perspective on the subject, but note that the program of the U.S. Nuclear Regulatory Commission and also that of the U.S. industry's Electric Power Research Institute include many international collaborative research efforts. Without any doubt, nuclear safety research today is international in scope, and the collaborative movement is gaining in strength

  1. Progress of nuclear safety research. 2002

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

    2002-11-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

  2. Commissioning of research reactors. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

  3. Reactor safety research - results and perspectives

    International Nuclear Information System (INIS)

    Banaschik, M.

    1989-01-01

    The work performed so far is an essential contribution to the determination of the safety margins of nuclear facilities and their systems and to the further development of safety engineering. The further development of safety engineering involves a shift of emphasis in reactor safety research towards event sequences beyond the design basis. The aim of this shift in emphasis is the further development of the preventive level. This is based on the fact that the conservative design of the operating and safety systems involves and essential safety potential. The R and D work is intended to help develop accident management measures and to take the plant back into the safe state even after severe accidents. In this context, it is necessary to make full use of the safety margins of the plant and to include the operating systems for coping with accidents. As a result of the aims, the research work approaches operating and plant-specific processes. (orig./DG) [de

  4. Accelerator Fusion Research Division 1991 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    Berkner, Klaus H.

    1991-12-01

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

  5. Accelerator & Fusion Research Division 1991 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

  6. NASA Lewis Research Center's materials and structures division

    International Nuclear Information System (INIS)

    Weymueller, C.R.

    1976-01-01

    Research activities at the NASA Lewis Research Center on materials and structures are discussed. Programs are noted on powder metallurgy superalloys, eutectic alloys, dispersion strengthened alloys and composite materials. Discussions are included on materials applications, coatings, fracture mechanics, and fatigue

  7. Accelerator ampersand Fusion Research Division 1991 summary of activities

    International Nuclear Information System (INIS)

    1991-12-01

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations

  8. Accelerator and fusion research division. 1992 Summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-01

    This report contains brief discussions on research topics in the following area: Heavy-Ion Fusion Accelerator Research; Magnetic Fusion Energy; Advanced Light Source; Center for Beam Physics; Superconducting Magnets; and Bevalac Operations.

  9. Annual report of the Division of Thermonuclear Fusion Research and the Division of Large Tokamak Development for the period of April 1, 1977 to March 31, 1978

    International Nuclear Information System (INIS)

    1979-02-01

    Research and development works in fiscal year 1977 of the Division of Thermonuclear Fusion Research and the Division of Large Tokamak Development are described. 1) Theoretical studies on tokamak confinement have continued with more emphasis on computations. A task was started of developing a computer code system for mhd behavior of tokamak plasmas. 2) Experimental studies of lower hybrid heating up to 140 kW were made in JFT-2. The ion temperature was increased by 50% -- 60% near the plasma center. Plasma-wall interactions (particle and thermal fluxes to the wall, and titanium gettering) were studied. In JFT-2a (DIVA) ion sputtering, arcing and evaporation were identified, and the impurity ion sputtering was found to be a dominant origin of metal impurities in the present tokamaks. High temperature and high-density plasma divertor actions were demonstrated; i.e. the divertor decreases the radiation power loss by a factor of 3 and increases the energy confinement time by a factor of 2.5. Various diagnostic instruments operated sufficiently to provide useful information for the research with JFT-2 and JFT-2a(DIVA). 3) JFT-2 and JFT-2a(DIVA) operated as scheduled. Technological improvements were made such as titanium coating of the chamber wall, discharge cleaning and pre-ionization. 4) Detailed design of the prototype JT-60 neutral beam injector was made. A 200 kW, 650 MHz radiofrequency heating system for JFT-2 was completed; a lower hybrid heating experiment in JFT-2 was successful 5) In particle-surface interactions, the sputtering and surface erosion were studied. 6) Improvement designs of a superconducting cluster test facility and a test module coil were made in the toroidal coil development. 7) Second preliminary design of the tokamak experimental fusion reactor JXFR started in April 1977. Safety analyses were made of the main components and system of JXFR on the basis of the first preliminary design. (J.P.N.)

  10. Research on the improvement of nuclear safety

    International Nuclear Information System (INIS)

    Yoo, Keon Joong; Kim, Dong Soo; Kim, Hui Dong; Park, Chang Kyu

    1993-06-01

    To improve the nuclear safety, this project is divided into three areas which are the development of safety analysis technology, the development of severe accident analysis technology and the development of integrated safety assessment technology. 1. The development of safety analysis technology. The present research aims at the development of necessary technologies for nuclear safety analysis in Korea. Establishment of the safety analysis technologies enables to reduce the expenditure both by eliminating excessive conservatisms incorporated in nuclear reactor design and by increasing safety margins in operation. It also contributes to improving plant safety through realistic analyses of the Emergency Operating Procedures (EOP). 2. The development of severe accident analysis technology. By the computer codes (MELCOR and CONTAIN), the in-vessel and the ex-vessel severe accident phenomena are simulated. 3. The development of integrated safety assessment technology. In the development of integrated safety assessment techniques, the included research areas are the improvement of PSA computer codes, the basic study on the methodology for human reliability analysis (HRA) and common cause failure (CCF). For the development of the level 2 PSA computer code, the basic research for the interface between level 1 and 2 PSA, the methodology for the treatment of containment event tree are performed. Also the new technologies such as artificial intelligence, object-oriented programming techniques are used for the improvement of computer code and the assessment techniques

  11. Nuclear safety research in HGF 2011

    International Nuclear Information System (INIS)

    Tromm, Walter

    2012-01-01

    After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out as safe as possible is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the

  12. Materials and Molecular Research Division annual report, 1977

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    Progress in research in structure of materials, mechanical, and physical properties, solid state physics, and materials chemistry, including chemical structure, high temperature and surface chemistry, is reported. (FS)

  13. The NIAID Division of AIDS enterprise information system: integrated decision support for global clinical research programs

    Science.gov (United States)

    Gupta, Nitin; Varghese, Suresh; Virkar, Hemant

    2011-01-01

    The National Institute of Allergy and Infectious Diseases (NIAID) Division of AIDS (DAIDS) Enterprise Information System (DAIDS-ES) is a web-based system that supports NIAID in the scientific, strategic, and tactical management of its global clinical research programs for HIV/AIDS vaccines, prevention, and therapeutics. Different from most commercial clinical trials information systems, which are typically protocol-driven, the DAIDS-ES was built to exchange information with those types of systems and integrate it in ways that help scientific program directors lead the research effort and keep pace with the complex and ever-changing global HIV/AIDS pandemic. Whereas commercially available clinical trials support systems are not usually disease-focused, DAIDS-ES was specifically designed to capture and incorporate unique scientific, demographic, and logistical aspects of HIV/AIDS treatment, prevention, and vaccine research in order to provide a rich source of information to guide informed decision-making. Sharing data across its internal components and with external systems, using defined vocabularies, open standards and flexible interfaces, the DAIDS-ES enables NIAID, its global collaborators and stakeholders, access to timely, quality information about NIAID-supported clinical trials which is utilized to: (1) analyze the research portfolio, assess capacity, identify opportunities, and avoid redundancies; (2) help support study safety, quality, ethics, and regulatory compliance; (3) conduct evidence-based policy analysis and business process re-engineering for improved efficiency. This report summarizes how the DAIDS-ES was conceptualized, how it differs from typical clinical trial support systems, the rationale for key design choices, and examples of how it is being used to advance the efficiency and effectiveness of NIAID's HIV/AIDS clinical research programs. PMID:21816958

  14. Proceedings of fuel safety research specialists' meeting

    International Nuclear Information System (INIS)

    Suzuki, Motoe

    2002-08-01

    Fuel Safety Research Specialists' Meeting, which was organized by Japan Atomic Energy Research Institute, was held on March 4-5, 2002 at JAERI in Tokai Establishment. Purposes of the Meeting are to exchange information and views on LWR fuel safety topics among the specialist participants from domestic and foreign organizations, and to discuss the recent and future fuel research activities in JAERI. In the Meeting, presentations were given and discussions were made on general report of fuel safety research activities, fuel behaviors in normal operation and accident conditions, FP release behaviors in severe accident conditions, and JAERI's ''Advanced LWR Fuel Performance and Safety Research Program''. A poster exhibition was also carried out. The Meeting significantly contributed to planning future program and cooperation in fuel research. This proceeding integrates all the pictures and papers presented in the Meeting. The 10 of the presented papers are indexed individually. (J.P.N.)

  15. Safety management in research and development organisation

    International Nuclear Information System (INIS)

    Nivedha, T.

    2016-01-01

    Health and safety is one of the most important aspects of an organizations smooth and effective functioning. It depends on the safety management, health management, motivation, leadership and training, welfare facilities, accident statistics, policy, organization and administration, hazard control and risk analysis, monitoring, statistics and reporting. Workplace accidents are increasingly common, main causes are untidiness, noise, too hot or cold environments, old or poorly maintained machines, and lack of training or carelessness of employees. One of the biggest issues facing employers today is the safety of their employees. This study aims at analyzing the occupational health and safety of Research organization in Indira Gandhi Centre for Atomic Research by gathering information on health management, safety management, motivation, leadership and training, welfare facilities, accident statistics, organization and administration, hazard control and risk analysis, monitoring, statistics and reporting. Data were collected by using questionnaires which were developed on health and safety management system. (author)

  16. Applied Science Division annual report, Environmental Research Program FY 1983

    International Nuclear Information System (INIS)

    Cairns, E.J.; Novakov, T.

    1984-05-01

    The primary concern of the Environmental Research Program is the understanding of pollutant formation, transport, and transformation and the impacts of pollutants on the environment. These impacts include global, regional, and local effects on the atmosphere and hydrosphere, and on certain aspects of human health. This multidisciplinary research program includes fundamental and applied research in physics, chemistry, engineering, and biology, as well as research on the development of advanced methods of measurement and analysis. During FY 1983, research concentrated on atmospheric physics and chemistry, applied physics and laser spectroscopy, combustion theory and phenomena, environmental effects of oil shale processing, freshwater ecology and acid precipitation, trace element analysis for the investigation of present and historical environmental impacts, and a continuing survey of instrumentation for environmental monitoring

  17. Light water reactor safety research project

    International Nuclear Information System (INIS)

    Markoczy, G.; Aksan, S.N.; Behringer, K.; Prodan, M.; Stierli, F.; Ullrich, G.

    1980-07-01

    The research and development activities for the safety of Light Water Power Reactors carried out 1979 at the Swiss Federal Institute for Reactor Research are described. Considerations concerning the necessity, objectives and size of the Safety Research Project are presented, followed by a detailed discussion of the activities in the five tasks of the program, covering fracture mechanics and nondestructive testing, thermal-hydraulics, reactor noise analysis and pressure vessel steel surveillance. (Auth.)

  18. 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

  19. Nuclear Safety Research Department annual report 2000

    International Nuclear Information System (INIS)

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

    2001-08-01

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

  20. Outline of criticality safety research project

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Tachimori, Shoichi; Suzaki, Takenori; Takeshita, Isao; Miyoshi, Yoshinori; Nakajima, Ken; Sakurai, Satoshi; Yanagisawa, Hiroshi

    1987-01-01

    As the power generation capacity of LWRs in Japan increased, the establishment and development of nuclear fuel cycle have become the important subject. Conforming to the safety research project of the nation, the Japan Atomic Energy Research Institute has advanced the project of constructing a new research facility, that is, Nuclear Fuel Cycle Engineering Research Facility (NUCEF). In this facility, it is planned to carry out the research on criticality safety, upgraded reprocessing techniques, and the treatment and disposal of transuranium element wastes. In this paper, the subjects of criticality safety research and the research carried out with a criticality safety experiment facility which is expected to be installed in the NUCEF are briefly reported. The experimental data obtained from the criticality safety handbooks and published literatures in foreign countries are short of the data on the mixture of low enriched uranium and plutonium which is treated in the reprocessing of spent fuel from LWRs. The acquisition of the criticality data for various forms of fuel, the elucidation of the scenario of criticality accidents, and the soundness of the confinement system for gaseous fission products and plutonium are the main subjects. The Static Criticality Safety Facility, Transient Criticality Safety Facility and pulse column system are the main facilities. (Kako, I.)

  1. Safety of research reactors - A regulator's perspective

    International Nuclear Information System (INIS)

    Rahman, M.S.

    2001-01-01

    Due to historical reasons research reactors have received less regulatory attention in the world than nuclear power plants. This has given rise to several safety issues which, if not addressed immediately, may result in an undesirable situation. However, in Pakistan, research reactors and power reactors have received due attention from the regulatory authority. The Pakistan Research Reactor-1 has been under regulatory surveillance since 1965, the year of its commissioning. The second reactor has also undergone all the safety reviews and checks mandated by the licensing procedures. A brief description of the regulatory framework, the several safety reviews carried out have been briefly described in this paper. Significant activities of the regulatory authority have also been described in verifying the safety of research reactors in Pakistan along with the future activities. The views of the Pakistani regulatory authority on the specific issues identified by the IAEA have been presented along with specific recommendations to the IAEA. We are of the opinion that there are more Member States operating nuclear research reactors than nuclear power plants. Therefore, there should be more emphasis on the research reactor safety, which somehow has not been the case. In several recommendations made to the IAEA on the specific safety issues the emphasis has been, in general, to have a similar documentation and approach for maintaining and verifying operational safety at research reactors as is currently available for nuclear power reactors and may be planned for nuclear fuel cycle facilities. (author)

  2. Accelerator and Fusion Research Division: 1987 summary of activities

    Energy Technology Data Exchange (ETDEWEB)

    1988-04-01

    An overview of the design and the initial studies for the Advanced Light Source is given. The research efforts for the Center for X-Ray Optics include x-ray imaging, multilayer mirror technology, x-ray sources and detectors, spectroscopy and scattering, and synchrotron radiation projects. The Accelerator Operations highlights include the research by users in nuclear physics, biology and medicine. The upgrade of the Bevalac is also discussed. The High Energy Physics Technology review includes the development of superconducting magnets and superconducting cables. A review of the Heavy-Ion Fusion Accelerator Research is also presented. The Magnetic Fusion Energy research included the development of ion sources, accelerators for negative ions, diagnostics, and theoretical plasma physics. (WRF)

  3. Accelerator and Fusion Research Division: 1987 summary of activities

    International Nuclear Information System (INIS)

    1988-04-01

    An overview of the design and the initial studies for the Advanced Light Source is given. The research efforts for the Center for X-Ray Optics include x-ray imaging, multilayer mirror technology, x-ray sources and detectors, spectroscopy and scattering, and synchrotron radiation projects. The Accelerator Operations highlights include the research by users in nuclear physics, biology and medicine. The upgrade of the Bevalac is also discussed. The High Energy Physics Technology review includes the development of superconducting magnets and superconducting cables. A review of the Heavy-Ion Fusion Accelerator Research is also presented. The Magnetic Fusion Energy research included the development of ion sources, accelerators for negative ions, diagnostics, and theoretical plasma physics

  4. Environmental Sciences Division: Summaries of research in FY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This report focuses on research in global change, as well as environmental remediation. Global change research investigates the following: distribution and balance of radiative heat energy; identification of the sources and sinks of greenhouse gases; and prediction of changes in the climate and concomitant ecological effects. Environmental remediation develops the basic understanding needed to remediate soils, sediments, and ground water that have undergone radioactive and chemical contamination.

  5. Summary of fuel safety research meeting 2004

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

    2004-10-01

    Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

  6. Seismic safety research program plan

    International Nuclear Information System (INIS)

    1987-05-01

    This document presents a plan for seismic research to be performed by the Structural and Seismic Engineering Branch in the Office of Nuclear Regulatory Research. The plan describes the regulatory needs and related research necessary to address the following issues: uncertainties in seismic hazard, earthquakes larger than the design basis, seismic vulnerabilities, shifts in building frequency, piping design, and the adequacy of current criteria and methods. In addition to presenting current and proposed research within the NRC, the plan discusses research sponsored by other domestic and foreign sources

  7. Research and development activities of the Neutron Physics Division for the period January 1977-December 1978

    International Nuclear Information System (INIS)

    Ramanadham, M.; Joneja, O.P.

    1979-01-01

    The research and development programmes of the Neutron Physics Division of the Bhabha Atomic Research Centre, Bombay, for the period 1977-1978 are outlined. The fields covered include reactor (neutron) physics, fusion and plasma neutronics, biological and high precision crystallography, solid state phenomena and seismology as well as the associated workshop facilities. (K.B.)

  8. RESEARCH AREA -- ARTIFICIAL INTELLIGENCE CONTROL (AIR POLLUTION TECHNOLOGY BRANCH, AIR POLLUTION PREVENTION AND CONTROL DIVISION, NRMRL)

    Science.gov (United States)

    The Air Pollution Technology Branch (APTB) of NRMRL's Air Pollution Prevention and Control Division in Research Triangle Park, NC, has conducted several research projects for evaluating the use of artificial intelligence (AI) to improve the control of pollution control systems an...

  9. Materials and Molecular Research Division annual report 1980

    International Nuclear Information System (INIS)

    1981-06-01

    Progress made in the following research areas is reported: materials sciences (metallurgy and ceramics, solid state physics, materials chemistry); chemical sciences (fundamental interactions, processes and techniques); nuclear sciences; fossil energy; advanced isotope separation technology; energy storage; magnetic fusion energy; and nuclear waste management

  10. Annual Report 2011-2012 (RAND National Security Research Division)

    Science.gov (United States)

    2012-01-01

    Reports & Bookstore Make a charitable contribution Limited Electronic Distribution Rights This document and trademark(s) contained herein are protected by...research team included a former CEO of the Australian Defence Science and Technology Organisation , as well as former officials from U .S . subma- rine

  11. Materials and Molecular Research Division annual report 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-06-01

    Progress made in the following research areas is reported: materials sciences (metallurgy and ceramics, solid state physics, materials chemistry); chemical sciences (fundamental interactions, processes and techniques); nuclear sciences; fossil energy; advanced isotope separation technology; energy storage; magnetic fusion energy; and nuclear waste management.

  12. About the Nutritional Science Research Group | Division of Cancer Prevention

    Science.gov (United States)

    The Nutritional Science Research Group (NSRG) promotes and supports studies establishing a comprehensive understanding of the precise role of diet and food components in modulating cancer risk and tumor cell behavior. This focus includes approaches to characterize molecular targets and variability in individual responses to nutrients and dietary patterns. |

  13. Progress of nuclear safety research, 1990

    International Nuclear Information System (INIS)

    1990-07-01

    Since the Japan Atomic Energy Research Institute (JAERI) was founded as a nonprofit, general research and development organization for the peaceful use of nuclear energy, it has actively pursued the research and development of nuclear energy. Nuclear energy is the primary source of energy in Japan where energy resources are scarce. The safety research is recognized at JAERI as one of the important issues to be clarified, and the safety research on nuclear power generation, nuclear fuel cycle, waste management and environmental safety has been conducted systematically since 1973. As of the end of 1989, 38 reactors were in operation in Japan, and the nuclear electric power generated in 1988 reached 29 % of the total electric power generated. 50 years have passed since nuclear fission was discovered in 1939. The objective of the safety research at JAERI is to earn public support and trust for the use of nuclear energy. The overview of the safety research at JAERI, fuel behavior, reliability of reactor structures and components, reactor thermal-hydraulics during LOCA, safety assessment of nuclear power plants and nuclear fuel cycle facilities, radioactive waste management and environmental radioactivity are reported. (K.I.)

  14. Research on PWR safety in France

    International Nuclear Information System (INIS)

    Zammite, R.

    1988-07-01

    The French nuclear safety arrangements form a centralized system characterized by cooperation between the government authorities, their technical advisers and the operators of the installations, especially between the Commissariat a l'Energie Atomique (CEA) and Electricite de France (EDF). This cooperation in no way contradicts the respective responsibilities of the different parties, in particular those of EDF regarding the safety of its installations and those of CEA as the government's technical adviser and safety analyst. However, it considerably affects the research on reactor safety, which is mainly performed by the CEA Institute for Nuclear Safety and Protection (IPSN), in collaboration with EDF. For PWRs, the safety preoccupations concerning their development, commissioning and operation can be divided into the following three categories: A. Safety in design and construction, B. Safety in operation and the control of potential accidents, C. Maintaining safety - aging problems. The effort consecrated to each category has varied in the past and will continue to do so in the future. At the present stage, emphasis is being given to categories B and C. The appendix includes tables which indicate, for categories A, B and C, the relationship between the existing research programmes and the questions remaining open that they are intended to solve

  15. Empirical Bayes methods in road safety research.

    NARCIS (Netherlands)

    Vogelesang, R.A.W.

    1997-01-01

    Road safety research is a wonderful combination of counting fatal accidents and using a toolkit containing prior, posterior, overdispersed Poisson, negative binomial and Gamma distributions, together with positive and negative regression effects, shrinkage estimators and fiercy debates concerning

  16. Nirex Safety Assessment Research Programme bibliography, 1990

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1990-10-01

    This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. (author)

  17. HTGR safety research concerns at NRC

    International Nuclear Information System (INIS)

    Minogue, R.B.

    1982-01-01

    A general discussion of HTGR technical and safety-related problems is given. The broad areas of current research programs specific to the Fort St. Vrain reactor and applicable to HTGR technology are summarized

  18. Minority University Research and Education Division (MURED) Update

    Science.gov (United States)

    Malone, John

    2000-01-01

    Program priorities include: (1) Expand and advance NASA's scientific and technological base by building on prior year's efforts in research and academic infrastructure; (2) Increase exposure to NASA's unique mission and facilities by developing closer relationships with NASA Strategic Enterprises; (3) Increase involvement in competitive peer review and merit selection processes; (4) Contribute significantly to the Agency's strategic goals and objectives; (5) Create systemic and sustainable change through partnerships and programs that enhance research and education programs; (6) Prepare faculty and students at HBCU's for NASA-related fields and increase number of students that enter and successfully complete degrees in NASA-related fields; (7) Establish measurable program goals and objectives; and (8) Improve financial management performance.

  19. IRSN safety research carried out for reviewing safety cases

    International Nuclear Information System (INIS)

    Serres, Ch.

    2010-01-01

    Christophe Serres from IRSN (France) described the independent role of the IRSN regarding research related to nuclear safety in the context of the French Planning Act of 28 June 2006 foreseeing a licence application to be submitted in 2015 for the creation of a deep geological repository. IRSN research programme is organised along research activities devoted to addressing independently-identified k ey safety issues . These 'key issues' should also be of prime concern for the implementer since they relate to the demonstration of the overall safety of the repository, and the level of funding that the implementer should afford to research activities of concern for safety. He explained that the quality and independency of the research programme carried out by IRSN allow building and improving a set of scientific knowledge and technical skills that serves the public mission of delivering technical appraisal and advice, e.g., on behalf of the national safety authority. In particular they contribute to improving the decisional process by making possible scientific dialogue with stakeholders independently from regulator or implementer. The current IRSN R and D programme is developed along the following lines: - Test the adequacy of experimental methods for which feedback is not sufficient. - Develop basic scientific knowledge in the fields where there is a need for better understanding of complex phenomena and interactions. - Develop and use numerical modelling tools to support studies on complex phenomena and interactions. - Perform specific experimental tests aiming at assessing the key parameters that may warrant the performances of the different components of the repository. These studies are carried out by means of experiments performed either at IRSN surface laboratories, or in the Tournemire Experimental Station (TES), an underground facility operated by IRSN in the south-east of France. Targeted actions on research related to operational safety and reversibility

  20. Status of criticality safety research at NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, Ken [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Two critical facilities, named STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility), at the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) started their hot operations in 1995. Since then, basic experimental data for criticality safety research have been accumulated using STACY, and supercritical experiments for the study of criticality accident in a reprocessing plant have been performed using TRACY. In this paper, the outline of those critical facilities and the main results of TRACY experiments are presented. (author)

  1. Surveys of research in the Chemistry Division, Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Grazis, B.M. [ed.

    1992-11-01

    Research reports are presented on reactive intermediates in condensed phase (radiation chemistry, photochemistry), electron transfer and energy conversion, photosynthesis and solar energy conversion, metal cluster chemistry, chemical dynamics in gas phase, photoionization-photoelectrons, characterization and reactivity of coal and coal macerals, premium coal sample program, chemical separations, heavy elements coordination chemistry, heavy elements photophysics/photochemistry, f-electron interactions, radiation chemistry of high-level wastes (gas generation in waste tanks), ultrafast molecular electronic devices, and nuclear medicine. Separate abstracts have been prepared. Accelerator activites and computer system/network services are also reported.

  2. Surveys of research in the Chemistry Division, Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Grazis, B.M. (ed.)

    1992-01-01

    Research reports are presented on reactive intermediates in condensed phase (radiation chemistry, photochemistry), electron transfer and energy conversion, photosynthesis and solar energy conversion, metal cluster chemistry, chemical dynamics in gas phase, photoionization-photoelectrons, characterization and reactivity of coal and coal macerals, premium coal sample program, chemical separations, heavy elements coordination chemistry, heavy elements photophysics/photochemistry, f-electron interactions, radiation chemistry of high-level wastes (gas generation in waste tanks), ultrafast molecular electronic devices, and nuclear medicine. Separate abstracts have been prepared. Accelerator activites and computer system/network services are also reported.

  3. USA NRC/RSR Data Bank System and Reactor Safety Research Data Repository (RSRDR)

    International Nuclear Information System (INIS)

    Maskewitz, B.F.; Bankert, S.F.

    1979-01-01

    The United States Nuclear Regulatory Commission (NRC), through its Division of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research, has established the NRC/RSR Data Bank Program to collect, process, and make available data from the many domestic and foreign water reactor safety research programs. An increasing number of requests for data and/or calculations generated by NRC Contractors led to the initiation of the program which allows timely and direct access to water reactor safety data in a manner most useful to the user. The program consists of three main elements: data sources, service organizations, and a data repository

  4. Reactor safety research in France

    International Nuclear Information System (INIS)

    Bussac, J.; Zammite, R.

    1989-01-01

    The paper deals withs PWR research only and covers programs performed in CEA or in cooperation between CEA and EDF or Framatome. Emphasis is being given to core cooling faults and associated procedures, primary circuit two-phase thermohydraulics, core damage, safeguarding of confinement, evaluation of accidental releases, and management of accident consequences. Most of the design and construction adequacy problems have already been solved in a generic manner, nevertheless new designs are now being studied and may require complementary research. (DG)

  5. Combustion research in the Internal Fluid Mechanics Division

    Science.gov (United States)

    Mularz, Edward J.

    1986-01-01

    The goal of this research is to bring computational fluid dynamics to a state of practical application for the aircraft engine industry. The approach is to have a strongly integrated computational and experimental program for all the disciplines associated with the gas turbine and other aeropropulsion systems by advancing the understanding of flow physics, heat transfer, and combustion processes. The computational and experimental research is integrated in the following way: the experiments that are performed provide an empirical data set so that physical models can be formulated to describe the processes that are occurring - for example, turbulence or chemical reaction. These experiments also form a data base for those who are doing code development by providing experimental data against which the codes can be verified and assesed. Models are generated as closure to some of the numerical codes, and they also provide physical insight for experiments. At the same time, codes which solve the complete Navier-Stokes equations can be used as a kind of numerical experiment from which far more extensive data can be obtained than ever could be obtained experimentally. This could provide physical insight into the complex processes that are taking place. These codes are also exercised against experimental data to assess the accuracy and applicability of models.

  6. Safety of research reactors (Design and Operation)

    International Nuclear Information System (INIS)

    Dirar, H. M.

    2012-06-01

    The primary objective of this thesis is to conduct a comprehensive up-to-date literature review on the current status of safety of research reactor both in design and operation providing the future trends in safety of research reactors. Data and technical information of variety selected historical research reactors were thoroughly reviewed and evaluated, furthermore illustrations of the material of fuel, control rods, shielding, moderators and coolants used were discussed. Insight study of some historical research reactors was carried with considering sample cases such as Chicago Pile-1, F-1 reactor, Chalk River Laboratories,. The National Research Experimental Reactor and others. The current status of research reactors and their geographical distribution, reactor category and utilization is also covered. Examples of some recent advanced reactors were studied like safety barriers of HANARO of Korea including safety doors of the hall and building entrance and finger print identification which prevent the reactor from sabotage. On the basis of the results of this research, it is apparent that a high quality of safety of nuclear reactors can be attained by achieving enough robust construction, designing components of high levels of efficiency, replacing the compounds of the reactor in order to avoid corrosion and degradation with age, coupled with experienced scientists and technical staffs to operate nuclear research facilities.(Author)

  7. Annual report of the Division of Thermonuclear Fusion Research, JAERI

    International Nuclear Information System (INIS)

    1977-02-01

    The JFT-2 operating regime was extended to higher toroidal field of 18 kG. Plasma confinements were studied on impurities, instabilities, plasma-wall interaction. Properties of a plasma with a separatrix magnetic surface and plasma behaviour in the scrape-off layer were studied in JFT-2a. In the diagnostics, a grazing-incidence vacuum ultra-violet spectrometer for studies on impurities was completed and put into operation. Several minor improvement and remodelling on the JFT-2 and JFT-2a tokamaks were carried out for the convenience of operation. In the plasma heating, constructions of the JFT-2 neutral injection system and the injector test stand ITS-2 for development of the higher energy ion source were started. The design of 200 kW RF power source for the plasma heating in JFT-2 was also made. Research in surface effects in fusion devices started at April 1, 1975. Experimental apparatus was designed and constructed in this fiscal year. A group for superconducting magnet development for fusion device was set up in January, 1976. Theoretical works continued in the analyses on transport processes, plasma heating, and mhd stabilities with an increasing effort on computational studies. A preliminary design of the 100 MW sub(t) tokamak experimental fusion reactor has been started in April, 1975. At the same time a conceptual design of the 2000 MW sub(t) power reactor was further improved. In the development of large tokamak device of next generation, programs on JT-60 and JT-4 are being carried out. Research and development works and detailed design studies on JT-60 are started based on the preliminary design studies made in the previous year. Preliminary design studies on JT-4 are completed. (auth.)

  8. Research of beryllium safety issues

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Dolan, T.J.; Hankins, M.R.; Pawelko, R.J.

    1993-01-01

    Beryllium has been identified as a leading contender for the plasma-facing material in ITER. Its use has some obvious advantages, but there are also a number of safety concerns associated with it. The Idaho National Engineering Laboratory (INEL) has undertaken a number of studies to help resolve some of these issues. One issue is the response of beryllium to neutron irradiation. We have tested samples irradiated in the Advanced Test Reactor (ATR) and are currently preparing to make measurements of the change in mechanical properties of beryllium samples irradiated at elevated temperatures in the Fast Flux Test Facility (FFTF) and the Experimental Breeder Reactor II (EBR-II) at the INEL. Mechanical tests will be conducted at the irradiation temperatures of 375-550 C. Other experiments address permeation and retention of implanted tritium in plasma-sprayed beryllium. In one test the porosity of the material allowed 0.12% of implanted ions and 0.17% of atoms from background gas pressure to pass through the foil with essentially no delay. For comparison, similar tests on fully dense hot-rolled, vacuum melted or sintered powder foils of high purity beryllium showed only 0.001% of implanting ions to pass through the foil, and then only after a delay of several hours. None of the molecular gas appeared to permeate these latter targets. An implication is that plasma-sprayed beryllium may substantially enhance recycling of tritium to the plasma provided it is affixed to a relatively impermeable substrate. (orig.)

  9. Nuclear reactor safety research in Idaho

    International Nuclear Information System (INIS)

    Zeile, H.J.

    1983-01-01

    Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

  10. Probabilistic safety assessment for research reactors

    International Nuclear Information System (INIS)

    1986-12-01

    Increasing interest in using Probabilistic Safety Assessment (PSA) methods for research reactor safety is being observed in many countries throughout the world. This is mainly because of the great ability of this approach in achieving safe and reliable operation of research reactors. There is also a need to assist developing countries to apply Probabilistic Safety Assessment to existing nuclear facilities which are simpler and therefore less complicated to analyse than a large Nuclear Power Plant. It may be important, therefore, to develop PSA for research reactors. This might also help to better understand the safety characteristics of the reactor and to base any backfitting on a cost-benefit analysis which would ensure that only necessary changes are made. This document touches on all the key aspects of PSA but placed greater emphasis on so-called systems analysis aspects rather than the in-plant or ex-plant consequences

  11. NASA's aviation safety research and technology program

    Science.gov (United States)

    Fichtl, G. H.

    1977-01-01

    Aviation safety is challenged by the practical necessity of compromising inherent factors of design, environment, and operation. If accidents are to be avoided these factors must be controlled to a degree not often required by other transport modes. The operational problems which challenge safety seem to occur most often in the interfaces within and between the design, the environment, and operations where mismatches occur due to ignorance or lack of sufficient understanding of these interactions. Under this report the following topics are summarized: (1) The nature of operating problems, (2) NASA aviation safety research, (3) clear air turbulence characterization and prediction, (4) CAT detection, (5) Measurement of Atmospheric Turbulence (MAT) Program, (6) Lightning, (7) Thunderstorm gust fronts, (8) Aircraft ground operating problems, (9) Aircraft fire technology, (10) Crashworthiness research, (11) Aircraft wake vortex hazard research, and (12) Aviation safety reporting system.

  12. Experts' discussion on reactor safety research

    International Nuclear Information System (INIS)

    1980-01-01

    The experts' discussion on reactor safety research deals with risk analysis, political realization, man and technics, as well as with the international state of affairs. Inspite of a controversy on individual issues and on the proportion of governmental and industrial involvment in reactor safety research, the continuation and intensification of corresponding research work is said to be necessary. Several participants demanded to consider possible 'conventional accidents' as well as a stronger financial commitment by the industry in this sector. The ratio 'man and technics' being an interface decisive for the proper functioning or failure of complex technical systems requires even more research work to be done. (GL) [de

  13. Program nuclear safety research: report 2000

    International Nuclear Information System (INIS)

    Muehl, B.

    2001-09-01

    The reactor safety R and D work of forschungszentrum karlsruhe (FZK) had been part of the nuclear safety research project (PSF) since 1990. In 2000, a new organisational structure was introduced and the Nuclear Safety Research Project was transferred into the nuclear safety research programme (NUKLEAR). In addition to the three traditional main topics - Light Water Reactor safety, Innovative systems, Studies related to the transmutation of actinides -, the new Programme NUKLEAR also covers Safety research related to final waste storage and Immobilisation of HAW. These new topics, however, will only be dealt with in the next annual report. Some tasks related to the traditional topics have been concluded and do no longer appear in the annual report; other tasks are new and are described for the first time. Numerous institutes of the research centre contribute to the work 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 2001. (orig.)

  14. The IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Abou Yehia, H.

    2007-01-01

    According to the research reactor database of IAEA (RRDB), 250 reactors are operating worldwide, 248 have been shut down and 170 have been decommissioned. Among the 248 reactors that do not run, some will resume their activities, others will be dismantled and the rest do not face a clear future. The analysis of reported incidents shows that the ageing process is a major cause of failures, more than two thirds of operating reactors are over 30 years old. It also appears that the lack of adequate regulations or safety standards for research reactors is an important issue concerning reactor safety particularly when reactors are facing re-starting or upgrading or modifications. The IAEA has launched a 4-axis program: 1) to set basic safety regulations and standards for research reactors, 2) to provide IAEA members with an efficient help for the application of these safety regulations to their reactors, 3) to foster international exchange of information on research reactor safety, and 4) to provide IAEA members with a help concerning safety issues linked to malicious acts or sabotage on research reactors

  15. HOW DO WORK HIERARCHIES AND STRICT DIVISIONS OF LABOUR IMPACT CARE WORKERS' EXPERIENCES OF HEALTH AND SAFETY? CASE STUDIESOF LONG TERM CARE IN TORONTO.

    Science.gov (United States)

    Syed, I; Daly, T; Armstrong, P; Lowndes, R; Chadoin, M; Naidoo, V

    2016-01-01

    According to the Canadian Health Care Association (1), there are 2,577 long-term care ("LTC") facilities across Canada, with the largest proportion (33.4%) located in Ontario. Most studies focus on residents' health, with less attention paid to the health and safety experiences of staff. Given that the work performed in Ontario LTC facilities is very gendered, increasingly racialized, task-oriented, and with strict divisions of labour, this paper explores in what ways some of these factors impact workers' experiences of health and safety. The study objectives included the following research question: How are work hierarchies and task orientation experienced by staff? This paper draws on data from rapid team-based ethnographies of the shifting division of labour in LTC due to use of informal carers in six non-profit LTC facilities located in Toronto, Ontario. Our method involved conducting observations and key informant interviews (N=167) with registered nurses, registered practical nurses, personal support workers, dietary aides, recreation therapists, families, privately paid companions, students, and volunteers. Interviews were audio-recorded, transcribed verbatim, and thematically analyzed. For observations, researchers were paired and covered shifts between 7 a.m. and 11 p.m., as well as into the late night over six days, at each of the six sites. Detailed ethnographic field notes were written during and immediately following observational fieldwork. Our results indicate that employee stress is linked to the experiences of care work hierarchies, task orientation, and strict divisions of labour between and among various staff designations. Findings from this project confirm and extend current research that demonstrates there are challenging working conditions in LTC, which can result in occupational health and safety problems, as well as stress for individual workers.

  16. IAEA activities on research reactor safety

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.

    1995-01-01

    Since its inception in 1957, the International Atomic Energy Agency (IAEA) has included activities in its programme to address aspects of research reactors such as safety, utilization and fuel cycle considerations. These activities were based on statutory functions and responsibilities, and on the current situation of research reactors in operation around the world; they responded to IAEA Member States' general or specific demands. At present, the IAEA activities on research reactors cover the above aspects and respond to specific and current issues, amongst which safety-related are of major concern to Member States. The present IAEA Research Reactor Safety Programme (RRSP) is a response to the current situation of about 300 research reactors in operation in 59 countries around the world. (orig.)

  17. Nuclear safety research at the European Commission's Joint Research Centre

    International Nuclear Information System (INIS)

    Toerroenen, K.

    2003-01-01

    Nuclear power plants currently generate some 35 % of electricity used in the European Union and applicant countries. Nuclear safety will therefore remain a priority for the EU, particularly in view of enlargement, the need to monitor ageing nuclear installations and the licencing of advanced new reactor systems. The European Commission's Joint Research Centre (JRC), with its long involvement and recognised competence in nuclear safety related activities, provides direct support to the European Commission services responsible for nuclear safety and civil protection. (author)

  18. Proceedings of the seminar on nuclear safety research and the workshop on reactor safety research

    International Nuclear Information System (INIS)

    2001-07-01

    The seminar on the nuclear safety research was held on November 20, 2000 according to the start of new five year safety research plan (FY2001-2005: established by Nuclear Safety Commission) with 79 participants. In the seminar, Commissioner Dr. Kanagawa gave the outline of the next five year safety research plan. Following this presentation, progresses and future scopes of safety researches in the fields of reactor facility, fuel cycle facility, radioactive waste and environmental impact on radiation at Japan Atomic Energy Research Institute (JAERI) were reported. After the seminar, the workshop on reactor safety research was held on November 21-22, 2000 with 141 participants. In the workshop, four sessions titled safety of efficient and economic utilization of nuclear fuel, safety related to long-term utilization of power reactors, research on common safety-related issues and toward further improvement of nuclear safety were organized and, outcomes and future perspectives in these wide research R and D in the related area at other organizations including NUPEC, JAPEIC and Kansai Electric Power Co. was presented in each session. This report compiles outlines of the presentations and used materials in the seminar and the workshop to form the proceedings for the both meetings. (author)

  19. The John Milner Nutrition and Cancer Prevention Research Practicum | Division of Cancer Prevention

    Science.gov (United States)

    The Nutritional Science Research Group in the Division of Cancer Prevention at the National Cancer Institute, National Institutes of Health and the Department of Nutrition at the Clinical Center, National Institutes of Health, and the U.S. Department of Agriculture’s Beltsville Human Nutrition Research Center are offering a one-week educational opportunity in Nutrition and Cancer Prevention Research for individuals with a sustained commitment to nutrition and health promotion. |

  20. Reactor safety research in times of change

    International Nuclear Information System (INIS)

    Zipper, Reinhard

    2013-01-01

    Since the early 1970ies reactor safety research sponsored by the German Ministry of Economics an Technology and its predecessors and pursued independently from interests of industry or industrial associations as well as from current licensing issues significantly contributed to the extension of knowledge regarding risks and possible threats associated with the operation of nuclear power plants. The results of these research activities triggered several measures taken by industry and utilities to further enhance the internationally recognized high safety standards of nuclear power plants in Germany. Furthermore, by including especially universities in the distinguished research activities a large number of young scientists were given the opportunity to qualify in the field of nuclear reactor technology and safety thus contributing to the preservation of competence during the demographic change. The nuclear phase out in Germany affects also issues of reactor safety research in Germany. While Germany will progressively decrease and terminate the use of nuclear energy for public power supply other countries in Europe and in other parts of the world are continuing, expanding and even starting the use of nuclear power. As generally recognized, nuclear safety is an international issue and in the wake of the Fukushima disaster there are several initiatives to launch a system of internationally binding safety rules and guide lines. The German Competence Alliance therefore has elaborated a framework of areas were future reactor safety research will still be needed to support German efforts based on own and independent expertise to continuously develop and establish highest safety standards for the use of nuclear power supply domestic and abroad.

  1. Current status of nuclear safety research

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Efforts at nuclear safety research have expanded year by year in Japan, in term of money and technical achievement. The Atomic Energy Commission set last year the five year nuclear safety research program, a guideline by which various research institutes will be able to develop their own efforts in a concerted manner. From the results of the nuclear safety research which cover very wide areas ranging from reactor engineering safety, safety of nuclear fuel cycle facilities, prevention of radiation hazards to the adequate treatment and disposal of radioactive wastes, AIJ hereafter focuses of LWR engineering safety and prevents two articles, one introducing the current results of the NSSR program developed by JAERI and the other reporting the LWR reliability demonstration testing projects being promoted by MITI. The outline of these demonstration tests was reported in this report. The tests consist of earthquake resistance reliability test of nuclear power plants, steam generator reliability tests, valve integrity tests, fuel assembly reliability tests, reliability tests of heat affected zones and reliability tests of pumps. (Kobatake, H.)

  2. Los Alamos Life Sciences Division's biomedical and environmental research programs. Progress report, January-December 1980

    International Nuclear Information System (INIS)

    Holland, L.M.; Stafford, C.G.; Bolen, S.K.

    1981-09-01

    Highlights of research progress accomplished in the Life Sciences Division during the year ending December 1980 are summarized. Reports from the following groups are included: Toxicology, Biophysics, Genetics; Environmental Pathology, Organic Chemistry, and Environmental Sciences. Individual abstracts have been prepared for 46 items for inclusion in the Energy Data Base

  3. Active Barrett's Esophagus Translational Research Network Grants | Division of Cancer Prevention

    Science.gov (United States)

    The Division of Cancer Prevention (DCP) conducts and supports research to determine a person's risk of cancer and to find ways to reduce the risk. This knowledge is critical to making progress against cancer because risk varies over the lifespan as genetic and epigenetic changes can transform healthy tissue into invasive cancer.

  4. H-Division annual report of research activities, December 1, 1947-- December 1, 1948

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1949-04-19

    This volume constitutes part 2 of the H-Division, Los Alamos National Laboratory, Annual Report of Research Activities for December 1, 1947 to December 1, 1948. Full reports of ten projects involving exposure of man or rodents to various forms of radiation are described. The individual reports are separately indexed and abstracted for the database.

  5. Radiological and Environmental Research Division annual report, July 1979-June 1980. [Lead abstract

    Energy Technology Data Exchange (ETDEWEB)

    Rowland, R.E.; Stehney, A.F.

    1981-05-01

    Separate abstracts were prepared for 19 of the 33 papers presented by the Center for Human Radiobiology for the Radiological and Environmental Research Division Annual Report. The 14 items not included are abstracts only and deal with the mechanisms and dosimetry for induction of malignancies by radium. (KRM)

  6. Seismic safety margins research program overview

    International Nuclear Information System (INIS)

    Tokarz, F.J.; Smith, P.D.

    1978-01-01

    A multiyear seismic research program has been initiated at the Lawrence Livermore Laboratory. This program, the Seismic Safety Margins Research Program (SSMRP) is funded by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The program is designed to develop a probabilistic systems methodology for determining the seismic safety margins of nuclear power plants. Phase I, extending some 22 months, began in July 1978 at a funding level of approximately $4.3 million. Here we present an overview of the SSMRP. Included are discussions on the program objective, the approach to meet the program goal and objectives, end products, the probabilistic systems methodology, and planned activities for Phase I

  7. 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)

  8. IRSN research programs concerning reactor safety

    International Nuclear Information System (INIS)

    Bardelay, J.

    2005-01-01

    This paper is made up of 3 parts. The first part briefly presents the missions of IRSN (French research institute on nuclear safety), the second part reviews the research works currently led by IRSN in the following fields : -) the assessment of safety computer codes, -) thermohydraulics, -) reactor ageing, -) reactivity accidents, -) loss of coolant, -) reactor pool dewatering, -) core meltdown, -) vapor explosion, and -) fission product release. In the third part, IRSN is shown to give a major importance to experimental programs led on research or test reactors for collecting valid data because of the complexity of the physical processes that are involved. IRSN plans to develop a research program concerning the safety of high or very high temperature reactors. (A.C.)

  9. MAPLE research reactor safety uncertainty assessment methodology

    International Nuclear Information System (INIS)

    Sills, H.E.; Duffey, R.B.; Andres, T.H.

    1999-01-01

    The MAPLE (multipurpose Applied Physics Lattice Experiment) reactor is a low pressure, low temperature, open-tank-in pool type research reactor that operates at a power level of 5 to 35 MW. MAPLE is designed for ease of operation, maintenance, and to meet today's most demanding requirements for safety and licensing. The emphasis is on the use of passive safety systems and environmentally qualified components. Key safety features include two independent and diverse shutdown systems, two parallel and independent cooling loops, fail safe operation, and a building design that incorporates the concepts of primary containment supported by secondary confinement

  10. Research program on regulatory safety research - Synthesis report 2008

    International Nuclear Information System (INIS)

    Mailaender, R

    2009-06-01

    This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2008 and the results obtained. The main points of the research program, which is co-ordinated by the Swiss Federal Nuclear Safety Inspectorate ENSI, are discussed. Topics covered concern reactor safety as well as human, organisational and safety aspects. Work done in several areas concerning reactor safety and materials as well as interactions in severe accidents in light-water reactors is described. Radiation protection, the transport and disposal of radioactive wastes and safety culture are also looked at. Finally, national and international co-operation is briefly looked at and work to be done in 2009 is reviewed. The report is completed with a list of research and development projects co-ordinated by ENSI

  11. Safety status of Russian research reactors

    International Nuclear Information System (INIS)

    Morozov, S.I.

    2001-01-01

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety at nuclear research facilities, including research reactors, critical assemblies and sub-critical assemblies. It implies implementing three major activities: 1) establishing the laws and safety standards in the field of research reactors nuclear and radiation safety; 2) research reactors licensing; and 3) inspections (or license conditions tracking and inspection). The database on nuclear research facilities has recently been updated based on the actual status of all facilities. It turned out that many facilities have been shutdown, whether temporary or permanently, waiting for the final decision on their decommissioning. Compared to previous years the situation has been inevitably changing. Now we have 99 nuclear research facilities in total under Gosatomnadzor of Russia supervision (compared to 113 in previous years). Their distribution by types and operating organizations is presented. The licensing and conduct of inspection processes are briefly outlined with emphasis being made on specific issues related to major incidents that happened in 2000, spent fuel management, occupational exposure, effluents and emissions, emergency preparedness and physical protection. Finally, a summary of problems at current Russian research facilities is outlined. (author)

  12. Nuclear safety research in HGF 2012

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German Federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out safe is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the partners in the

  13. RATU2, research for safety and operability

    International Nuclear Information System (INIS)

    Solin, J.

    1998-01-01

    The Finnish research programme on the structural integrity of nuclear power plants, RATU2 was launched in 1995 for four years to coordinate the independent national research and development work aiming for structural safety in NPP's. The general planning and goal setting of the programme was based on the research need assessment and evaluation of the previous RATU programme. The research plans have been updated and refined annually on the basis of available funding. The RATU2 programme is briefly introduced in this paper. The role of RATU2 in the national nuclear energy research field, the research areas, administrative data, main objectives and future plans are reported in this paper

  14. Occupational health, waste management, and environmental research program of the Health Division 1981. Progress report

    International Nuclear Information System (INIS)

    Voelz, G.L.

    1983-09-01

    The primary responsibility of the Health Division at the Los Alamos National Laboratory is to provide effective programs in health, safety, waste processing, and environmental protection for the Laboratory. During 1981, evaluations of respiratory protective equipment included 3 special DOE contractor supplied-air suits or hoods and 10 commercial supplied-air devices. Preliminary results of chemical permeation tests of different protective garment materials are reported. Industrial hygiene field studies of oil shale work were conducted at the Geokinetics true in situ facility and the Rio Blanco modified in situ facility. An occupational medical survey of workers at the Geokinetics, Inc., facility was completed. Research on the generation and characterization of aerosols was continued for inhalation studies of man-made mineral fibers and oil shale aerosols. The distribution of 241 Am in a whole body was determined by tissue analyses. Preliminary results of mortality in workers formerly employed at the Rocky Flats plant were reported. A simplified method for the analysis of plutonium in urine has been developed. Instrumentation development resulted in a portable computer system for field data analysis and a small, computerized, wristwatch-style radiation dosimeter. Environmental surveillance at Los Alamos during 1981 showed the highest estimated radiation dose due to Laboratory operations is about 4% of the dose due to the natural radioactivity here. A study was completed on alternative strategies for long-term management of Los Alamos transuranic wastes. A successful 10-day test burn of pentachlorophenol-contaminated wastes was conducted in the Controlled Air Incinerator. Decontamination factors for five fission products in the off-gas handling system of the incinerator were measured

  15. The emphasis is on reactor safety research

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    For the second time the Association for Reactor Safety mbH (GRS), Koeln, organised on behalf of the BMFT the conference 'Reactor safety research'. About 400 visitors took part. The public who were interested were given a review of the activities which are being undertaken by the BMFT in the programme 'Research and safety of light-water reactors'. The series of conference papers initiated by the BMFT is to be developed into a permanent information source which will be of interest to those working on nuclear questions such as official quarters, industry and high schools, and experts who have to give judgements. The most important statements by various research groups in industry, high schools and also associations of experts, are summarised. (orig.) [de

  16. Stakeholder Safety in Information Systems Research

    Directory of Open Access Journals (Sweden)

    R.H. Barbour

    2006-11-01

    Full Text Available Information Communication Technology (ICT researchers adapt and use tools from reference and cognate disciplines. This application of existing tools outside the context of their development has implications beyond the immediate problem context. ICT researchers have access to a wide variety of data sources including newer ones, such as the Internet, that may bring unexpected outcomes. ICT research can impact on researchers, their institutions and the researched in unexpected ways. People so affected are the stakeholders in ICT research activities. Reputations, welfare and property may be put at risk by unplanned events described in this paper. Legal aspects of ICT research are broadly identified and linked to the tort of negligence. The Social Research Association’s Code for researcher safety is described and its application extended to include the Internet as a potential data source. A common set of underlying ethical principles is identified suggesting that the ICT researcher can refine particular research protocols for specific social contexts.

  17. Research and development activities of the Neutron Physics Division for the period January 1980 - December 1980

    International Nuclear Information System (INIS)

    Basu, T.K.; Bhakay-Tamhane, S.

    1981-01-01

    The highlights of the research and development (R and D) activities of the Neutron Physics Division of the Bhabha Atomic Research Centre, Bombay, during January - December 1980 are summarised. The R and D activities are in the fields of critical and subcritical fission systems, the plasma focus device, applied neutron physics, neutron and X-ray crystallography, materials physics and seismology. (M.G.B.)

  18. Reactor safety research. The CEC contribution

    International Nuclear Information System (INIS)

    Krischer, W.

    1990-01-01

    The involvement of the EC Commission in the reactor safety research dates back almost to the implementation of the EURATOM Treaty and has thus lasted for thirty years. The need for close collaboration and for general consensus on some crucial problems of concern to the public, has made the role of international organizations and, as far as Europe is concerned, the role of the European Community particularly important. The areas in which the CEC has been active during the last five years are widespread. This is partly due to the fact that, after TMI and Chernobyl, the effort and the interest of the different countries in reactor safety was considerable. Reactor Safety Research represents the proceedings of a seminar held by the Commission at the end of its research programme 1984-88 on reactor safety. As such it gives a comprehensive overview of the recent activities and main results achieved in the CEC Joint Research Centre and in national laboratories throughout Europe on the basis of shared cost actions. In a concluding chapter the book reports on the opinions, expressed during a panel by a group of major exponents, on the needs for future research. The main topics addressed are, with particular reference to Light Water Reactors (LWRS): reliability and risk evaluation, inspection of steel components, primary circuit components end-of-life prediction, and abnormal behaviour of reactor cooling systems. As far as LMFBRs are concerned, the topics covered are: severe accident modelling, material properties and structural behaviour studies. There are 67 pages, all of which are indexed separately. Reactor Safety Research will be of particular interest to reliability and safety engineers, nuclear engineers and technicians, and mechanical and structural engineers. (author)

  19. Love, Legislation, and OSHA [Occupational Safety and Health Act]: Highlights from the Manpower Division

    Science.gov (United States)

    Vadnais, Arthur

    1974-01-01

    The conference of the Manpower Division of the American Vocational Association is summarized. Skill centers, relevant Federal legislation, student-instructor relationship, curriculum development, and organization business items were among the topics discussed. (AG)

  20. Transport safety research abstracts. No. 1

    International Nuclear Information System (INIS)

    1991-07-01

    The Transport Safety Research Abstracts is a collection of reports from Member States of the International Atomic Energy Agency, and other international organizations on research in progress or just completed in the area of safe transport of radioactive material. The main aim of TSRA is to draw attention to work that is about to be published, thus enabling interested parties to obtain further information through direct correspondence with the investigators. Information contained in this issue covers work being undertaken in 6 Member States and contracted by 1 international organization; it is hoped with succeeding issues that TSRA will be able to widen this base. TSRA is modelled after other IAEA publications describing work in progress in other programme areas, namely Health Physics Research Abstracts (No. 14 was published in 1989), Waste Management Research Abstracts (No. 20 was published in 1990), and Nuclear Safety Research Abstracts (No. 2 was published in 1990)

  1. 77 FR 40622 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2012-07-10

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH..., oxygen supply partnership, safety culture, occupational health and safety management systems, preventing...

  2. High Energy Physics Division semiannual report of research activities. Semi-annual progress report, July 1, 1995--December 31, 1995

    International Nuclear Information System (INIS)

    Norem, J.; Bajt, D.; Rezmer, R.; Wagner, R.

    1996-10-01

    This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period July 1, 1995 - December 31, 1995. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included

  3. Summary of fuel safety research meeting 2005

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

    2006-03-01

    Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

  4. NRC/DAE reactor safety research Data Bank

    International Nuclear Information System (INIS)

    Laats, E.T.

    1982-01-01

    In 1976, the United States Nuclear Regulatory Commission (NRC) established the NRC/Division of Accident Evaluation (DAE) Data Bank to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. This program has since grown from the conceptual stage to a useful, usable service for computer code development, code assessment, and experimentation groups in meeting the needs of the nuclear industry. Data from 20 facilities are now processed and permanently stored in the Data Bank, which utilizes the Control Data Corporation (CDC) CYBER 176 computer system located at the Idaho National Engineering Laboratory (INEL). New data and data sources are continually being added to the Data Bank. In addition to providing data storage and access software, the Data Bank program supplies data entry, documentation, and training and advisory services to users and the NRC. Management of the NRC/DAE Data Bank is provided by EG and G Idaho, Inc

  5. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    International Nuclear Information System (INIS)

    1987-05-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions

  6. Safety upgrades to the NRU research reactor

    International Nuclear Information System (INIS)

    DeAbreu, B.; Mark, J.M.; Mutterback, E.J.

    1998-01-01

    The NRU (National Research Universal) Reactor is a 135 MW thermal research facility located at Chalk River Laboratories, and is owned and operated by Atomic Energy of Canada Limited. One of the largest and most versatile research reactors in the world, it serves as the R and D workhorse for Canada's CANDU business while at the same time filling the role as one of the world's major producers of medical radioisotopes. AECL plans to extend operation of the NRU reactor to approximately the year 2005 when a new replacement, the Irradiation Research Facility (IRF) will be available. To achieve this, AECL has undertaken a program of safety reassessment and upgrades to enhance the level of safety consistent with modem requirements. An engineering assessment/inspection of critical systems, equipment and components was completed and seven major safety upgrades are being designed and installed. These upgrades will significantly reduce the reactor's vulnerability to common mode failures and external hazards, with particular emphasis on seismic protection. The scheduled completion date for the project is 1999 December at a cost approximately twice the annual operating cost. All work on the NRU upgrade project is planned and integrated into the regular operating cycles of the reactor; no major outages are anticipated. This paper describes the safety upgrades and discusses the technical and managerial challenges involved in extending the operating life of the NRU reactor. (author)

  7. NRC safety research in support of regulation

    International Nuclear Information System (INIS)

    1994-06-01

    This report, the ninth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1993. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with sound technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission's rules, regulatory guides, or other guidance

  8. Time series modeling in traffic safety research.

    Science.gov (United States)

    Lavrenz, Steven M; Vlahogianni, Eleni I; Gkritza, Konstantina; Ke, Yue

    2018-08-01

    The use of statistical models for analyzing traffic safety (crash) data has been well-established. However, time series techniques have traditionally been underrepresented in the corresponding literature, due to challenges in data collection, along with a limited knowledge of proper methodology. In recent years, new types of high-resolution traffic safety data, especially in measuring driver behavior, have made time series modeling techniques an increasingly salient topic of study. Yet there remains a dearth of information to guide analysts in their use. This paper provides an overview of the state of the art in using time series models in traffic safety research, and discusses some of the fundamental techniques and considerations in classic time series modeling. It also presents ongoing and future opportunities for expanding the use of time series models, and explores newer modeling techniques, including computational intelligence models, which hold promise in effectively handling ever-larger data sets. The information contained herein is meant to guide safety researchers in understanding this broad area of transportation data analysis, and provide a framework for understanding safety trends that can influence policy-making. Copyright © 2017 Elsevier Ltd. All rights reserved.

  9. Annual report of Division of Thermonuclear Fusion Research and Division of Large Tokamak Development for the period of April 1, 1976 to March 31, 1977

    International Nuclear Information System (INIS)

    1978-02-01

    Research and development activities in the two divisions are closely related. 1) Theoretical and computational studies continued on tokamak confinement and heating related to experimental problems. Studies on NBI heating in JT-60 were completed. 2) Experimental studies on impurities, density control and effects of density fluctuations were made in JFT-2. Neutral beams up to 30 keV and 8 A were injected into JFT-2 plasma perpendicularly. The ion temperature was increased by 10% - 15%, which is in agreement with the prediction by classical Fokker-Planck theory. In JFT-2a(DIVA), plasma-wall interaction (behavior of heavy and light impurities) was studies. The divertor of DIVA reduced the plasma-wall interaction and hence the radiation loss due to heavy impurities by a factor of 3. A grazing-incidence vacuum monochromator was first used in impurity studies in JFT-2 and JFT-2a. 3) Technological improvements were made raising efficiencies of operation, maintenance and plasma research. 4) Neutral beam injector test stand ITS-2 of 100 keV was completed. Construction of a 200 kW, 650 MHz radiofrequency heating system for JFT-2 was started. 5) Sputterings of molybdenum and pyrolytic graphite by low-energy protons and chemical reaction rates of pyrolytic graphite with protons were measured. Honeycomb structure greatly reduced the sputtered particles. 6) The superconducting magnet development group made the design of cluster test apparatus and the development of large current superconductor. 7) Phase-I preliminary design of experimental fusion reactor JXFR was completed and preliminary safety evaluation of JXFR was made. 8) Detailed design of JT-60 was completed in November 1976. Engineering development contracts were all completed by March 1977. 9) Engineering studies and tests on critical components of JT-4 with non-circular plasma cross section and divertors were made, after the preliminary design in fiscal year 1975. (auth.)

  10. Advanced research workshop: nuclear materials safety

    International Nuclear Information System (INIS)

    Jardine, L J; Moshkov, M M.

    1999-01-01

    The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of

  11. Fifty years of driving safety research.

    Science.gov (United States)

    Lee, John D

    2008-06-01

    This brief review covers the 50 years of driving-related research published in Human Factors, its contribution to driving safety, and emerging challenges. Many factors affect driving safety, making it difficult to assess the impact of specific factors such as driver age, cell phone distractions, or collision warnings. The author considers the research themes associated with the approximately 270 articles on driving published in Human Factors in the past 50 years. To a large extent, current and past research has explored similar themes and concepts. Many articles published in the first 25 years focused on issues such as driver impairment, individual differences, and perceptual limits. Articles published in the past 25 years address similar issues but also point toward vehicle technology that can exacerbate or mitigate the negative effect of these issues. Conceptual and computational models have played an important role in this research. Improved crash-worthiness has contributed to substantial improvements in driving safety over the past 50 years, but future improvements will depend on enhancing driver performance and perhaps, more important, improving driver behavior. Developing models to guide this research will become more challenging as new technology enters the vehicle and shifts the focus from driver performance to driver behavior. Over the past 50 years, Human Factors has accumulated a large base of driving-related research that remains relevant for many of today's design and policy concerns.

  12. Health, safety and environmental research program

    International Nuclear Information System (INIS)

    Dinner, P.J.

    1983-01-01

    This report outlines the Health, Safety and Environmental Research Program being undertaken by the CFFTP. The Program objectives, relationship to other CFFTP programs, implementation plans and expected outputs are stated. Opportunities to build upon the knowledge and experience gained in safely managing tritium in the CANDU program, by addressing generic questions pertinent to tritium safety for fusion facilities, are identified. These opportunities exist across a broad spectrum of issues covering the anticipated behaviour of tritium in fusion facilities, the surrounding environment and in man

  13. LWR safety research at EPRI: an update

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Kalra, S.P.

    1983-01-01

    The philosophy, objectives, approach, and updated status of the Electric Power Research Institute's Light-Water-Reactor Safety Research Program are presented. In light of current industry needs, the major research and development emphases are described. The program focuses on providing enhanced capability via large-scale test projects, for understanding and predicting the behavior of nuclear power plants. This leads to a realistic quantification of the safety margins and to ways of improving reliability, availability, and productivity and thus to significant economic benefits for the nuclear industry. The major accomplishments resulting from various projects in the program categories of risk assessment, code development and validation, and analysis and testing are presented with the goal of technology transfer to the nuclear industry

  14. 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)

  15. Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    . The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  16. Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

    International Nuclear Information System (INIS)

    2011-01-01

    . The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  17. Medical Sciences Division report for 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This year's Medical Sciences Division (MSD) Report is organized to show how programs in our division contribute to the core competencies of Oak Ridge Institute for Science and Education (ORISE). ORISE's core competencies in education and training, environmental and safety evaluation and analysis, occupational and environmental health, and enabling research support the overall mission of the US Department of Energy (DOE)

  18. Lesbian women and household labor division: A systematic review of scholarly research from 2000 to 2015.

    Science.gov (United States)

    Brewster, Melanie E

    2017-01-02

    Recent studies have begun to attend to distribution of household labor within same-gender couples compared to heterosexual couples, yet much of the available research with lesbian couples has attempted to superimpose division of household labor frameworks developed with heterosexual couples (e.g., gender role socialization, exchange bargaining theories) to fit the experiences of same-gender couples. Using two academic search databases, the present article provides a systematic review of the available 28 peer-reviewed articles published from 2000-2015 about lesbian partnerships and household labor divisions. Results indicate that lesbian couples engage in a more equal distribution of household labor than heterosexual couples, and that lesbian women often opt to eschew traditional gendered divisions of chores in favor of other factors such as quality of task or ability. The systematic review uncovered notable constraints in the demography of participants (e.g., race, socioeconomic status, geographic location) across studies. Strategies for deepening the depth and breadth of this line of work for future researchers, and implications for relationship satisfaction are also discussed.

  19. Theoretical Division progress report

    International Nuclear Information System (INIS)

    Cooper, N.G.

    1979-04-01

    This report presents highlights of activities in the Theoretical (T) Division from October 1976-January 1979. The report is divided into three parts. Part I presents an overview of the Division: its unique function at the Los Alamos Scientific Laboratory (LASL) and within the scientific community as a whole; the organization of personnel; the main areas of research; and a survey of recent T-Division initiatives. This overview is followed by a survey of the 13 groups within the Division, their main responsibilities, interests, and expertise, consulting activities, and recent scientific accomplisments. The remainder of the report, Parts II and III, is devoted to articles on selected research activities. Recent efforts on topics of immediate interest to energy and weapons programs at LASL and elsewhere are described in Part II, Major National Programs. Separate articles present T-Divison contributions to weapons research, reactor safety and reactor physics research, fusion research, laser isotope separation, and other energy research. Each article is a compilation of independent projects within T Division, all related to but addressing different aspects of the major program. Part III is organized by subject discipline, and describes recent scientific advances of fundamental interest. An introduction, defining the scope and general nature of T-Division efforts within a given discipline, is followed by articles on the research topics selected. The reporting is done by the scientists involved in the research, and an attempt is made to communicate to a general audience. Some data are given incidentally; more technical presentations of the research accomplished may be found among the 47 pages of references. 110 figures, 5 tables

  20. Management of nanomaterials safety in research environment.

    Science.gov (United States)

    Groso, Amela; Petri-Fink, Alke; Magrez, Arnaud; Riediker, Michael; Meyer, Thierry

    2010-12-10

    Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health). The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3--highest hazard to Nano1--lowest hazard). Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material) are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal). The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and management are promoting

  1. Management of nanomaterials safety in research environment

    Directory of Open Access Journals (Sweden)

    Riediker Michael

    2010-12-01

    Full Text Available Abstract Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health. The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3 - highest hazard to Nano1 - lowest hazard. Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal. The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and

  2. Safety research for LWR type reactors

    International Nuclear Information System (INIS)

    1989-07-01

    The current R and D activities are to be seen in connection with the LWR risk assessment studies. Two trends are emerging, of which the one concentrates more on BWR-specific problems, and the other on the efficiency or safety-related assessment of accident management activities. This annual report of 1988 reviews the progress of work done by the institutes and departments of the Karlsruhe Nuclear Research Center, (KfK), or on behalf of KfK by external institutions, in the field of safety research. The papers of this report present the state of work at the end of the year 1988. They are written in German, with an abstract in English. (orig./HP) [de

  3. Accelerator and Fusion Research Division annual report, October 1981-September 1982. Fiscal year 1982

    International Nuclear Information System (INIS)

    Johnson, R.K.; Bouret, C.

    1983-05-01

    This report covers the activities of LBL's Accelerator and Fusion Research Division (AFRD) during 1982. In nuclear physics, the Uranium Beams Improvement Project was concluded early in the year, and experimentation to exploit the new capabilities began in earnest. Technical improvement of the Bevalac during the year centered on a heavy-ion radiofrequency quadrupole (RFQ) as part of the local injector upgrade, and we collaborated in studies of high-energy heavy-ion collision facilities. The Division continued its collaboration with Fermilab to design a beam-cooling system for the Tevatron I proton-antiprotron collider and to engineer the needed cooling components for the antiproton. The high-field magnet program set yet another record for field strength in an accelerator-type dipole magnet (9.2 T at 1.8 K). The Division developed the design for the Advanced Light Source (ALS), a 1.3-GeV electron storage ring designed explicitly (with low beam emittance and 12 long straight sections) to generate high-brilliance synchrotron light from insertion devices. The Division's Magnetic Fusion Energy group continued to support major experiments at the Princeton Plasma Physics Laboratory, the Lawrence Livermore National Laboratory (LLNL), and General Atomic Co. by developing positive-ion-based neutral-beam injectors. Progress was made toward converting our major source-test facility into a long-pulse national facility, the Neutral Beam Engineering Test Facility, which was completed on schedule and within budget in 1983. Heavy Ion Fusion research focused on planning, theoretical studies, and beam-transport experiments leading toward a High Temperature Experiment - a major test of this promising backup approach to fusion energy

  4. Nordic reactor safety research 1981-85

    International Nuclear Information System (INIS)

    Micheelsen, B.

    1986-01-01

    National resources in Denmark, Finland, Norway, and Sweden were put together with Nordic funds in the four-year research programme 1981-85 on selected areas of nuclear safety. The outcome of the programme, edited in four separate reports, is summarized, and important findings are listed in the areas of probabilistic risk assessment (PRA), loss-of-coolant accidents with small breaks, heat-transfer correlations, and corrosion in the nuclear industry. (author)

  5. Hydrogen problems in reactor safety research

    International Nuclear Information System (INIS)

    Casper, H.

    1984-01-01

    The BMFT and BMI have initiated a workshop 'Hydrogen Problems in Reactor Safety Research' that took place October 3./4., 1983. The objective of this workshop was to present the state of the art in the main areas - Hydrogen-Production - Hydrogen-Distribution - Hydrogen-Ignition - Hydrogen-Burning and Containment Behaviour - Mitigation Measures. The lectures on the different areas are compiled. The most important results of the final discussion are summarized as well. (orig.) [de

  6. Experimental and modeling studies of fire in compartments at Electricite de France, Research and Development Division

    International Nuclear Information System (INIS)

    Gautier, B.

    1997-12-01

    Since 1985, The Research and Development Division at Electricite de France has been in charge, through the development of the software MAGIC, to simulate the fire propagation in Nuclear Plants. The research program has included, since its beginning, an experimental activity dedicated to the combustion of fluids and electrical cables. This paper gives an overview of the works in progress and presents the latest results obtained, in particular in cable combustion. In this field, a three scale approach has been carried on, based on micro-thermo-gravimetry, calorimetry and real scale experiments. (author)

  7. Physics and safety of advanced research reactors

    International Nuclear Information System (INIS)

    Boening, K.; Hardt, P. von der

    1987-01-01

    Advanced research reactor concepts are presently being developed in order to meet the neutron-based research needs of the nineties. Among these research reactors, which are characterized by an average power density of 1-10 MW per liter, highest priority is now generally given to the 'beam tube reactors'. These provide very high values of the thermal neutron flux (10 14 -10 16 cm -2 s -1 ) in a large volume outside of the reactor core, which can be used for sample irradiations and, in particular, for neutron scattering experiments. The paper first discusses the 'inverse flux trap concept' and the main physical aspects of the design and optimization of beam tube reactors. After that two examples of advanced research reactor projects are described which may be considered as two opposite extremes with respect to the physical optimization principle just mentioned. The present situation concerning cross section libraries and neutronic computer codes is more or less satisfactory. The safety analyses of advanced research reactors can largely be updated from those of current new designs, partially taking advantage of the immense volume of work done for power reactors. The paper indicates a few areas where generic problems for advanced research reactor safety are to be solved. (orig.)

  8. 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

  9. 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)

  10. Role of in-house safety analysis and research activities in regulatory decision making

    International Nuclear Information System (INIS)

    Pradhan, Santosh K.; Nagrale, Dhanesh B.; Gaikwad, Avinash J.

    2015-01-01

    analysis and research activities in AERB, India with emphasis on Nuclear Safety Analysis Division. (author)

  11. Organizational safety factors research lessons learned

    International Nuclear Information System (INIS)

    Ryan, T.G.

    1995-01-01

    This Paper reports lessons learned and state of knowledge gained from an organizational factors research activity involving commercial nuclear power plants in the United States, through the end of 1991, as seen by the scientists immediately involved in the research. Lessons learned information was gathered from the research teams and individuals using a question and answer format. The following five questions were submitted to each team and individual: (1) What organizational factors appear to influence safety performance in some systematic way, (2) Should organizational factors research focus at the plant level, or should it extend beyond the plant level to the parent company, rate setting commissions, regulatory agencies, (3) How important is having direct access to plants for doing organizational factors research, (4) What lessons have been learned to date as the result of doing organizational factors research in a nuclear regulatory setting, and (5) What organizational research topics and issues should be pursued in the future? Conclusions based on the responses provided for this report are that organizational factors research can be conducted in a regulatory setting and produce useful results. Technologies pioneered in other academic, commercial, and military settings can be adopted for use in a nuclear regulatory setting. The future success of such research depends upon the cooperation of regulators, contractors, and the nuclear industry

  12. Barrier performance researches for the safety evaluation

    International Nuclear Information System (INIS)

    Niibori, Yuichi

    2004-01-01

    So far, many researches were conducted to propose a scientific evidence (a safety case) for the realization of geological disposal in Japan. In order to regulate the geological disposal system of radioactive wastes, on the other hand, we need also a holistic approach to integrate various data related for the performance evaluations of the engineered barrier system and the natural barrier system. However, the scientific bases are not sufficient to establish the safety regulation for such a natural system. For example, we often apply the specific probability density function (PDF) to the uncertainty of barrier system due to the essential heterogeneity. However, the applicability is not clear in the regulation point of view. A viewpoint to understand such an applicability of PDFs has been presented. (author)

  13. About the Mid-Continent Ecology Division (MED) of EPA's National Health and Environmental Effects Research Laboratory

    Science.gov (United States)

    The Mid-Continent Ecology Division (MED) conducts innovative research and predictive modeling to document and forecast the effects of pollutants on the integrity of watersheds and freshwater ecosystems.

  14. Safety evaluation of the Dalat research reactor operation

    International Nuclear Information System (INIS)

    Long, V.H.; Lam, P.V.; An, T.K.

    1989-01-01

    After an introduction presenting the essential characteristics of the Dalat Nuclear Research Reactor, the document presents i) The safety assurance condition of the reactor, ii) Its safety behaviour after 5 years of operation, iii) Safety research being realized on the reactor. Following is questionnaire of safety evaluation and a list of attachments, which concern the reactor

  15. Advancing Research and Practice: The Revised APA Division 30 Definition of Hypnosis.

    Science.gov (United States)

    Elkins, Gary R; Barabasz, Arreed F; Council, James R; Spiegel, David

    2015-04-01

    This article describes the history, rationale, and guidelines for developing a new definition of hypnosis by the Society of Psychological Hypnosis, Division 30 of the American Psychological Association. The definition was developed with the aim of being concise, being heuristic, and allowing for alternative theories of the mechanisms (to be determined in empirical scientific study). The definition of hypnosis is presented as well as definitions of the following related terms: hypnotic induction, hypnotizability, and hypnotherapy. The implications for advancing research and practice are discussed. The definitions are presented within the article.

  16. Technology Development, Evaluation, and Application (TDEA) FY 1995 progress report - Environmental, Safety, and Health (ESH) division

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, L.L.

    1996-09-01

    This report covers six months of effort, including startup time. Five projects were supported by the division: Pilot Program for the Risk-Based Surveillance of Lung Cancer in Los Alamos National Laboratory Workers, Optimization of Placement of Workplace Continuous Air Monitoring Instrumentation, A Polymeric Barrier Monitor to Protect Workers, Evaluation of a Real-Time Beryllium Detection Instrument and the Implications of Its Use, and High-Energy Dosimetry. A project summary for each is provided. An appendix to the report includes the 1995 Request for Proposals, Committee Members, Priority Technical Areas of Interest for FY95, Relative Prioritization and Weighting Factors, Format for Proposals, and Charter.

  17. Technology Development, Evaluation, and Application (TDEA) FY 1995 progress report - Environmental, Safety, and Health (ESH) division

    International Nuclear Information System (INIS)

    Andrews, L.L.

    1996-09-01

    This report covers six months of effort, including startup time. Five projects were supported by the division: Pilot Program for the Risk-Based Surveillance of Lung Cancer in Los Alamos National Laboratory Workers, Optimization of Placement of Workplace Continuous Air Monitoring Instrumentation, A Polymeric Barrier Monitor to Protect Workers, Evaluation of a Real-Time Beryllium Detection Instrument and the Implications of Its Use, and High-Energy Dosimetry. A project summary for each is provided. An appendix to the report includes the 1995 Request for Proposals, Committee Members, Priority Technical Areas of Interest for FY95, Relative Prioritization and Weighting Factors, Format for Proposals, and Charter

  18. The Nordic Research programme on nuclear safety

    International Nuclear Information System (INIS)

    1992-06-01

    Only two of the five Nordic countries (Denmark, Iceland, Finland, Norway and Sweden) - Sweden and Finland - operate nuclear power plants, but there are a number of nuclear installations close to their borders. Regular 4-year programmes were initiated in 1977, designated NKS-programmes. (NKS: Nordisk KerneSikkerhedsforskning - Nordic nuclear-safety research). The current fourth NKS-programme is, influenced by the Chernobyl accident, dominated by the necessity for acquiring knowledge on unexpected events and release of radioactive material from nuclear installations. The present programme is divided into the areas of emergency preparedness, waste and decommissioning, radioecology and reactor safety. It comprises a total of 18 projects, the results of which will later be published in the form of handbooks for use in cases of emergency etc. The future of joint Nordic project work in the nuclear safety field must be seen in the light of changing conditions in and around the Nordic countries, such as the opening of relations to neighbours in the east, the move towards the European Communities and the need for training a new generation of specialists in the nuclear field etc. Each project is described in considerable detail and a list of reports resulting from the third NKS-programme 1985-1989 is given. (AB)

  19. Safety and cost-effectiveness analysis of laparoscopic splenectomy by secondary pedicle division using monopolar electrocautery.

    Science.gov (United States)

    Zhou, Jianyin; Liu, Pingguo; Yin, Zhenyu; Zhao, Yilin; Wang, Xiaomin

    2013-09-01

    The expense of laparoscopic splenectomy (LS) has limited its use in developing countries, while medical costs are increasing worldwide. In this study, we performed LS by secondary pedicle division using monopolar electrocautery to achieve cost savings. Over seven years, we performed 45 consecutive LSs by secondary pedicle division using monopolar electrocautery (n=17) or ultrasonic shears (n=28) at a single center. These were reviewed to assess outcome and cost. Mean operating time was 179.7min, 7 conversions to open operation (15.6%) were necessary. There were four postoperative complications (8.9%) and no deaths. Twenty-three of 28 (82.1%) patients with idiopathic thrombocytopenic purpura developed a long-term positive response; and mean operative cost was RMB6,577 (US$1,034), which was much lower than that of Endo-GIATM in published reports. Between the monopolar electrocautery and ultrasonic shears groups, there were no significant differences in demographic characteristics or intraoperative and postoperative details, but operative cost was significantly lower in the former (RMB4,416, US$696 vs. RMB7,889, US$1,243; pelectrocautery is safe, efficacious and economical.

  20. The Geosciences Division of the Council on Undergraduate Research (GeoCUR): Supporting Faculty that Mentor Undergraduate Researchers

    Science.gov (United States)

    Fox, L. K.; Guertin, L. A.; Manley, P. L.; Fortner, S. K.

    2012-12-01

    Undergraduate research is a proven effective pedagogy that has a number of benefits including: enhancing student learning through mentoring relationships with faculty; increasing retention; increasing enrollment in graduate programs; developing critical thinking, creativity, problem solving and intellectual independence; and, developing an understanding of research methodology. Undergraduate research also has been demonstrated in preparing students for careers. In addition to developing disciplinary and technical expertise, participation in undergraduate research helps students improve communication skills (written, oral, and graphical) and time management. Early involvement in undergraduate research improves retention and, for those engaged at the 2YC level, helps students successfully transfers to 4YC. The Geosciences Division of the Council on Undergraduate Research (GeoCUR) supports faculty in their development of undergraduate research programs at all levels. GeoCUR leads workshops for new and future faculty covering all aspects of undergraduate research including incorporating research into coursework, project design, mentoring students, sustaining programs, and funding sources. GeoCUR members support new faculty by providing a range of services including: peer-review of grant proposals; advice on establishing an undergraduate research program; balancing teaching and research demands; and networking with other geoscientist. GeoCUR has also developed web resources that support faculty and departments in development of undergraduate research programs (http://serc.carleton.edu/NAGTWorkshops/undergraduate_research/index.html). This presentation will describe the services provided by GeoCUR and highlight examples of programs and resources available to geoscientists in all career stages for effective undergraduate research mentoring and development.

  1. Research and development activities of the Neutron Physics Division for the period January 1979-December 1979

    International Nuclear Information System (INIS)

    Basu, T.K.; Vohra, Y.K.

    1980-01-01

    Research and Development (R and D) activities of the Neutron Physics Division of the Bhabha Atomic Research Centre, Bombay during the calendar year 1979 are reported in the form of individual summaries. The Division's R and D work covers the fields of reactor neutron physics, applied neutronics, fusion plasma pinches, materials physics, crystallography and seismology. Some of the highlights of these activities are: (1) the development of a criticality formula for PURNIMA-II, a BeO reflected 233 U-uranyl nitrate solution critical experiment, (2) commissioning of a 21 K3, 50 KV fast capacitor bank for experiments of high-density plasma focus devices, (3) the design of a bore-hole model to develop carbon-oxygen logging method for identifying the oil and water zones in sand-stone formations in the earth's sub-surface using neutrons from a 14 MeV neutron generator, (4) proposal of a theoretical model for the equation of state of high-density matter in the intermediate pressure (approximately 10-100 Megabar) region, (5) development of a quantitative relation between the crater dimensions and the mound kinetic energy imparted by the shock from an underground nuclear explosion, and (6) texture studies of uranium fuel element samples using neutron diffraction. Progress of work on PURNIMA-II experiment, fusion blanket neutronics experiment, monitoring of nuclear explosions and discriminating them from earthquakes using seismic and microbarographic data is also reported. (M.G.B.)

  2. The organization of research reactor safety in the UKAEA

    International Nuclear Information System (INIS)

    Redpath, W.

    1983-01-01

    The present state of organization and development of research reactor safety in the UKAEA are outlined by addressing the fundamental safety principles which have been adopted in keeping with national health and safety requirement. The organisation, assessment and monitoring of research reactor safety on complex multi-discipline and multi-activity nuclear research and development site are discussed. Methods of safety assessment, such as probabilistic risk assessment and risk acceptance criteria, which have been developed and applied in practice are explained, and some indication of the directions in which some of the current developments in the safety of UKAEA research reactors is also included. (A.J.)

  3. A crucial step in cell division identified | Center for Cancer Research

    Science.gov (United States)

    When cell division doesn’t go according to plan, the resulting daughter cells can become unstable or even cancerous. A team of CCR investigators has now discovered a crucial step required for normal cell division to occur. Read more...

  4. 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

  5. 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.

  6. Determinants for conducting food safety culture research

    NARCIS (Netherlands)

    Nyarugwe, Shingai P.; Linnemann, Anita; Hofstede, Gert Jan; Fogliano, Vincenzo; Luning, Pieternel A.

    2016-01-01

    Background Foodborne outbreaks continue to occur regardless of existing food safety measures indicating the shortcomings of these measures to assure food safety. This has led to the recognition of food safety culture as a key contributory factor to the food safety performance of food

  7. AICD -- Advanced Industrial Concepts Division Biological and Chemical Technologies Research Program. 1993 Annual summary report

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, G.; Bair, K.; Ross, J. [eds.

    1994-03-01

    The annual summary report presents the fiscal year (FY) 1993 research activities and accomplishments for the United States Department of Energy (DOE) Biological and Chemical Technologies Research (BCTR) Program of the Advanced Industrial Concepts Division (AICD). This AICD program resides within the Office of Industrial Technologies (OIT) of the Office of Energy Efficiency and Renewable Energy (EE). The annual summary report for 1993 (ASR 93) contains the following: A program description (including BCTR program mission statement, historical background, relevance, goals and objectives), program structure and organization, selected technical and programmatic highlights for 1993, detailed descriptions of individual projects, a listing of program output, including a bibliography of published work, patents, and awards arising from work supported by BCTR.

  8. 75 FR 12554 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2010-03-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... priorities in mine safety and health research, including grants and contracts for such research, 30 U.S.C...

  9. Trends in fusion reactor safety research

    International Nuclear Information System (INIS)

    Herring, J.S.; Holland, D.F.; Piet, S.J.

    1991-01-01

    Fusion has the potential to be an attractive energy source. From the safety and environmental perspective, fusion must avoid concerns about catastrophic accidents and unsolvable waste disposal. In addition, fusion must achieve an acceptable level of risk from operational accidents that result in public exposure and economic loss. Finally, fusion reactors must control routine radioactive effluent, particularly tritium. Major progress in achieving this potential rests on development of low-activation materials or alternative fuels. The safety and performance of various material choices and fuels for commercial fusion reactors can be investigated relatively inexpensively through reactor design studies. These studies bring together experts in a wide range of backgrounds and force the group to either agree on a reactor design or identify areas for further study. Fusion reactors will be complex with distributed radioactive inventories. The next generation of experiments will be critical in demonstrating that acceptable levels of safe operation can be achieved. These machines will use materials which are available today and for which a large database exists (e.g. for 316 stainless steel). Researchers have developed a good understanding of the risks associated with operation of these devices. Specifically, consequences from coolant system failures, loss of vacuum events, tritium releases, and liquid metal reactions have been studied. Recent studies go beyond next step designs and investigate commercial reactor concerns including tritium release and liquid metal reactions. 18 refs

  10. Research on patient safety: falls and medications.

    Science.gov (United States)

    Boddice, Sandra Dawn; Kogan, Polina

    2009-10-01

    Below you will find summaries of published research describing investigations into patient safety issues related to falls and medications. The first summary provides details on the incidence of falls associated with the use of walkers and canes. This is followed by a summary of a fall-prevention intervention study that evaluated the effectiveness of widespread dissemination of evidence-based strategies in a community in Connecticut. The third write up provides information on three classes of medications that are associated with a significant number of emergency room visits. The last summary describes a pharmacist-managed medication reconciliation intervention pilot program. For additional details about the study findings and interventions, we encourage readers to review the original articles.

  11. Nirex Safety Assessment Research Programme bibliography, 1988

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1988-05-01

    This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. All work referred to has been funded, or partly funded, by UK Nirex Limited, previously known as the Nuclear Industry Radioactive Waste Executive (NIREX). The bibliography has been divided into two sections, a List of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the containers are emplaced, and the immediately adjacent geological formation disturbed by the construction of the repository. The far-field is the undisturbed geological formation between the near-field and the biosphere. (author)

  12. Nirex Safety Assessment Research Programme bibliography, 1987

    International Nuclear Information System (INIS)

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

    1987-06-01

    This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW). All work referred to has been funded, or partly funded, by UK Nirex Limited, previously known as the Nuclear Industry Radioactive Waste Executive (NIREX). The bibliography has been divided into two sections, a List of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the containers are emplaced, and the immediately adjacent geological formation disturbed by the construction of the repository. The far-field is the undisturbed geological formation between the near-field and the biosphere. (author)

  13. Division of Cyber Safety and Security Responsibilities Between Control System Owners and Suppliers

    OpenAIRE

    Skotnes , Ruth

    2016-01-01

    Part 2: CONTROL SYSTEMS SECURITY; International audience; The chapter discusses the important issue of responsibility for information and communications technology (ICT) – or cyber – safety and security for industrial control systems and the challenges involved in dividing the responsibility between industrial control system owners and suppliers in the Norwegian electric power supply industry. Industrial control system owners are increasingly adopting information and communications technologi...

  14. Fox Chase Cancer Center's Genitourinary Division: a national resource for research, innovation and patient care.

    Science.gov (United States)

    Uzzo, Robert G; Horwitz, Eric M; Plimack, Elizabeth R

    2016-04-01

    Founded in 1904, Fox Chase Cancer Center remains committed to its mission. It is one of 41 centers in the country designated as a Comprehensive Cancer Center by the National Cancer Institute, is a founding member of the National Comprehensive Cancer Network, holds the magnet designation for nursing excellence, is one of the first to establish a family cancer risk assessment program, and has achieved national distinction because of the scientific discoveries made there that have advanced clinical care. Two of its researchers have won Nobel prizes. The Genitourinary Division is nationally recognized and viewed as one of the top driving forces behind the growth of Fox Chase due to its commitment to initiating and participating in clinical trials, its prolific contributions to peer-reviewed publications and presentations at scientific meetings, its innovations in therapies and treatment strategies, and its commitment to bringing cutting-edge therapies to patients.

  15. Ontario Hydro Research Division's program for treatment of spent ion-exchange resins

    International Nuclear Information System (INIS)

    Nott, B.R.; Dodd, D.J.R.

    1981-09-01

    A brief review of the evolution of work programmes for chemical treatment of spent ion-exchange resins in Ontario Hydro's Research Division is presented. Attention has been focussed on pre-treatment processes for the treatment of the spent resins prior to encapsulation of the products in solid matrices. Spent Resin Regeneration and Acid Stripping processes were considered in some detail. Particular attention was paid to carbon-14 on spent resins, its determination in and removal from the spent resins (with the acid stripping technique). The use of separate cation and anion resin beds instead of mixed bed resins was examined with a view to reducing the volume of resin usage and consequently the volume of waste radioactive ion-exchange resin generated. (author)

  16. Activity Report of Reactor Physics Division - 1997

    International Nuclear Information System (INIS)

    Singh, Om Pal

    1998-01-01

    The research and development activities of the Reactor Physics Division of the Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam during 1997 are reported. The activities are arranged under the headings: nuclear data processing and validation, PFBR and KAMINI core physics, FBTR core physics, radioactivity and shielding and safety analysis. A list of publications of the Division and seminars delivered are included at the end of the report

  17. Health and safety at the Whiteshell Nuclear Research Establishment

    International Nuclear Information System (INIS)

    LeNeveu, D.M.

    1982-04-01

    This report outlines the health and safety program at the Whiteshell Nuclear Research Establishment. It describes the procedures in place to ensure that a high standard of conventional industrial and radiation safety is maintained in the workplace

  18. HTGR safety research program. Progress report, April--June 1975

    International Nuclear Information System (INIS)

    Kirk, W.L.

    1975-09-01

    Progress in HTGR safety research is reported under the following headings: fission product technology; primary coolant impurities; structural investigation; safety instrumentation and control systems; phenomena modeling and systems analysis. (JWR)

  19. Research and technology in the Federal Motor Carrier Safety Administration

    Science.gov (United States)

    2002-01-01

    As the Federal Government's chief commercial vehicle safety agency, the Federal Motor Carrier Safety Administration's (FMCSA), Office of Research and Technology (R&T) focuses on saving lives and reducing injuries by helping to prevent crashes involvi...

  20. Safety assessment of research reactors and preparation of the safety analysis report

    International Nuclear Information System (INIS)

    1994-01-01

    This Safety Guide presents guidelines, approved by international consensus, for the preparation, review and assessment of safety documentation for research reactors such as the Safety Analysis Report. While the Guide is most applicable to research reactors in the design and construction stage, it is also recommended for use during relicensing or reassessment of existing reactors

  1. 78 FR 40743 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2013-07-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... Director, NIOSH, on priorities in mine safety and health research, including grants and contracts for such...

  2. The Nirex safety assessment research programme

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1988-07-01

    This report describes progress on the Nirex Safety Assessment Research Programme in 1987/88. The programme is concerned with research into the disposal of low-level waste (LLW) and intermediate-level waste (ILW) into underground repositories. At the beginning of 1987/88 a range of techniques for measuring and modelling far-field phenomena were being applied to near-surface disposal of low-level waste in clay. However, during the year the far-field studies were redirected to consider generic geological materials of interest for deep disposal of low and intermediate-level waste, which is now the preferred option in the UK. A substantial 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 in quantifying this and laying the foundations for robust and reliable radiological assessments to be made with appropriate models. New projects have also been initiated to study the evolution and migration of gases from an underground repository and to consider the contribution of the biosphere to the retardation of radionuclides. (author)

  3. [50 years anniversary of Research Institute for Occupational Medicine and Human Ecology with Siberian Division of RAMSc].

    Science.gov (United States)

    Rukavishnikov, V S; Shaiakhmetov, S F; Gus'kova, T M

    2010-01-01

    The article covers main steps of establishment and development of Research Institute for Occupational medicine and Human ecology with Siberian Division of RAMSc over 50 years of activities, major results of research, contribution of the Institute personnel into development of hygienic science and practical medicine in Siberia.

  4. Role of nuclear safety research and future plan

    International Nuclear Information System (INIS)

    Kim, W. S.; Lee, J. I.; Kang, S. C.; Park, Y. W.; Lee, J. H.; Kim, M. W.; Lee, C. J.; Park, Y. I.

    2000-01-01

    For promoting and improving nuclear safety research activities, this report gives an insight on the scope of safety research and its role in the safety management of nuclear installations, and suggests measures to adequately utilize the research results through taking an optimized role share among research organizations. Several measures such as cooperative planning of common research areas and proper role assignment, improvement of the interfaces among researchers, and reflection of end-users' opinion in the course of planning and conducting research to promote application of research results are identified. It is expected that the identified measures will contribute to enhancing the efficiency and effectiveness of nuclear safety research, if they are implemented after deliberating with the government and safety research organizations

  5. Site Environmental Report for 2006. Volume I, Environment, Health, and Safety Division

    Energy Technology Data Exchange (ETDEWEB)

    None

    2007-09-30

    Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2006 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2006. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I is organized into an executive summary followed by six chapters that contain an overview of the Laboratory, a discussion of the Laboratory’s environmental management system, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from surveillance and monitoring activities.

  6. Research for the safety of existing nuclear facilities

    International Nuclear Information System (INIS)

    Teschendorff, Victor; Bruna, Giovanni B.; Gelder, Pieter de

    2007-01-01

    The essential role of research for maintaining the high safety standard for the existing nuclear installations is outlined in the context of internationally agreed needs. The three co-authoring Technical Safety Organisations are committed to continued safety research, recognising operational experience and new technologies as the main driving forces. The safety margin concept is introduced and new trends in traditional and new areas of safety research are identified. The importance of a sufficient experimental infrastructure and international co-operation in sustainable networks is highlighted. (orig.)

  7. Report of Activity, 1996 - 1997. Vol. 1. Experimental Research Division; Rapport d`activite 1996 - 1997. Tome 1. Division de Recherche Experimentale

    Energy Technology Data Exchange (ETDEWEB)

    Brunelle, Alain; Morlet, Marcel; Hutin, Christiane [eds.; Inst. de Physique Nucleaire, Paris-11 Univ., 91 - Orsay (France)

    1999-11-01

    This report presents the activity of Experimental Research Division of the Orsay Institute of Nuclear Physics on 1996 - 1997. The following 10 sections are represented through summary reports or short communications: 1. Nuclear structure far from stability (with the topics: 1.1. Exotic nuclei -Secondary beams of radioactive ions; 1.2. On-line spectroscopy; 1.3. Discrete high-spin states); 2. High excitation energy nuclear states; 3. Nuclear matter and nucleus-nucleus collisions (which includes 3.1. Evolution of reaction mechanisms from 10 to 150 MeV/u; 3.2. Hot nuclei; 3.3. Ultra-relativistic collisions); 4. Hadronic physics (with the topics: 4.1 Meson production; 4.2. Spin modes in nuclei; 4.3. Hadronic physics with electromagnetic probes); 5. Radiochemistry (with the sub-divisions: 5.1. Studies related to radioactive waste management; 5.2. Optical spectroscopy of actinide and lanthanide ions in solid media); 6. Inter-disciplinary research (with the topics: 6.1. Heavy ion and cluster interactions with matter and surfaces; 6.2. Medical imaging); 8. Teaching; 9. Publications - Conferences - Seminars; 10 Internal reports - Lectures - Theses - Patents. The scientific staff of the following groups is also presented: 1. Group of Nuclear Structure by Reactions; 2. Group of Heavy Ion Nuclear Physics; 3. Intermediary Energy Group; 4. Hadron Physics Group; 5. Nuclei-Ions-Matter Group; 6. Radiochemistry Group; 7. Group of Exotic Deformed Nuclei; 8. Group of Physics-Biology Interface

  8. Computational micromechanics of wind blade materials: recent activities at the Materials Research Division, Risoe DTU

    Energy Technology Data Exchange (ETDEWEB)

    Mishnaevsky Jr., L.; Broendsted, P.; Qing, H.; Wang, H.; Soerensen, Bent F. (Technical Univ. of Denmark, Riso National Lab. for Sustainable Energy. Materials Research Div., Roskilde (Denmark)); OEstergaard, R.C. (LM Wind Power Blades, Composite Mechanics, Roskilde (Denmark))

    2010-10-22

    Recent research works in the area of 3D computational microstructural modelling, virtual testing and numerical optimization of wind blade materials, carried out at the Materials Research Division, Rise DTU (Programme Composites and Materials Mechanics) are summarized. The works presented here have been carried out in the framework of several research projects: EU FP6 Upwind, Danida project 'Development of wind energy technologies in Nepal' and SinoDanish project '3D Virtual Testing of composites for wind energy applications' as well as the Framework Program 'Interface design of composite materials' and recently established Danish Centre for Composite Structures and Materials for Wind Turbines. Different groups of materials, which are used or have a potential for use for the wind turbine blades, are modelled with the use of the methods of the computational micromechanics, in particular: (1) glass and carbon fiber reinforced polymer composites used in the large wind turbine blades, (2) different sorts of timber, used in small wind turbines (first of all, in developing countries) and (3) nanoparticle reinforced polymer matrix composites (which have a potential to be used as components for future high strength wind blades). On the basis of the developed 3D microstructural finite element models of these materials, we analyzed the effect of their microstructures on damage resistance, strength and stiffness. The methods of the 3D model design and results of the simulations are discussed in this paper. (Author)

  9. Environmental effects research. Environmental Research Division annual report, January-December 1983. Part 3

    International Nuclear Information System (INIS)

    1984-12-01

    The Terrestrial Ecology group continued its involvement in the National Crop Loss Assessment Network, and studies of O 3 effects on winter wheat and soybeans were completed. Experiments on O 3 x SO 2 interactions on soybeans were also performed. The Microcosms for Acid Rain Studies (MARS) project had its first full year of research and much information concerning acid rain impacts on soil-plant systems was collected. A study of the influence of temporal variations in rain acidity on soybean productivity was also initiated. The aquatic radiochemistry group continued measurements of the mobility of plutonium and americium at a disposal site at Los Alamos and initiated similar work at Hanford. Laboratory tracer experiments were carried out to study the adsorptive behavior of neptunium, the solubility limits of plutonium, and the influence of rare earth concentration on the sorption and redox behavior of plutonium. The soil-plant process group initiated several studies on the influence of mycorrhizae to host plants in disturbed and natural environments. Much of the past research has been concerned with understanding mycorrhizal fungi propagule dynamics as related to disturbances associated with energy extraction. Future research will be directed at understanding how below-ground symbiotic associations may increase the fitness of host plants. Emphasis is being placed on resource acquisition and compartmental strategies. Separate analytics have been indexed for EDB

  10. Performance Data Report: Space Medicine Division, Human Research Program, Behavioural Health and Performance Research Element

    Science.gov (United States)

    Shea, Camille; Keeton, Kathryn E.; Schmidt, Lacey L.; Slack, Kelley J.; Patterson, Holly N.; Leveton, Lauren B.; Holland, Albert W.

    2012-01-01

    This report is the result of a collaborative effort between NASA?s Behavioral Health & Performance (BHP) Research and Operations Group to investigate and determine the availability of data pertaining to behavioral performance (and other pertinent variables) that have been collected by the laboratories at NASA?s Johnson Space Center. BHP?s Operations and Research groups collaborated to systematically identify what types of performance data are needed in relevant BHP performance domains and also to conduct structured interviews with NASA personnel to identify which data do or do not exist currently (and for instances where such data exist, to evaluate the type, quality, accessibility, and confidentiality of those data). The authors defined outcome categories of performance that encapsulate BHP performance domains, mapped BHP Research Risks and Gaps onto those performance outcome categories, and identified and prioritized indicators for each outcome category. The team identified key points of contact (subject matter experts [SMEs]) as potential interviewees, created a template for structured interview questions about sources and accessibility of performance data, and coordinated and conducted structured interviews with the SMEs. The methodology, results, and implications of this effort, as well as forward work needed, are discussed in this report.

  11. Environmental effects research. Environmental Research Division annual report, January-December 1983. Part 3

    Energy Technology Data Exchange (ETDEWEB)

    1984-12-01

    The Terrestrial Ecology group continued its involvement in the National Crop Loss Assessment Network, and studies of O/sub 3/ effects on winter wheat and soybeans were completed. Experiments on O/sub 3/ x SO/sub 2/ interactions on soybeans were also performed. The Microcosms for Acid Rain Studies (MARS) project had its first full year of research and much information concerning acid rain impacts on soil-plant systems was collected. A study of the influence of temporal variations in rain acidity on soybean productivity was also initiated. The aquatic radiochemistry group continued measurements of the mobility of plutonium and americium at a disposal site at Los Alamos and initiated similar work at Hanford. Laboratory tracer experiments were carried out to study the adsorptive behavior of neptunium, the solubility limits of plutonium, and the influence of rare earth concentration on the sorption and redox behavior of plutonium. The soil-plant process group initiated several studies on the influence of mycorrhizae to host plants in disturbed and natural environments. Much of the past research has been concerned with understanding mycorrhizal fungi propagule dynamics as related to disturbances associated with energy extraction. Future research will be directed at understanding how below-ground symbiotic associations may increase the fitness of host plants. Emphasis is being placed on resource acquisition and compartmental strategies. Separate analytics have been indexed for EDB.

  12. Ageing Management for Research Reactors. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  13. Ageing Management for Research Reactors. Specific Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  14. Nirex safety assessment research programme bibliography, 1991

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1991-09-01

    This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. The bibliography has been divided into two sections, a list of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste package, filling or sealing materials, and those parts of the host medium whose characteristics have been or could be altered by the repository or its content. The far-field is the rock formation outside the repository, including the surrounding strata, at a distance from the waste disposal site such that, for modelling purposes, the site may be considered as a single entity, and the effects of individual waste packages are indistinguishable in the effects of the whole. The far-field includes also the biosphere, into which radionuclides from the waste could conceivably migrate in the future. (author)

  15. Compilation of contract research for the Materials Engineering Branch, Division of Engineering

    International Nuclear Information System (INIS)

    1991-03-01

    This compilation of annual reports for FY 1990 by contractors to the Materials Engineering Branch of the Nuclear Regulatory Commission Office of Research concentrates on achievements in safety research for the primary system of commercial light water power reactors, particularly with regard to reactor vessels, primary system piping, steam generators, and nondestructive examination of primary system components. Separate abstracts have been prepared for each of the reports which are divided into the following categories: (1) vessel and piping fracture mechanics (including irradiation embrittlement); (2) pressure vessel surveillance dosimetry; (3) steam generators, aging, and environmental cracking; and (4) nondestructive examination techniques

  16. Site Environmental Report for 2004. Volume 1, Environment, Health, and Safety Division

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-09-30

    Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2004 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2004. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from these activities. This year, the Site Environmental Report was distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request.

  17. Innovations in Post-Marketing Safety Research

    NARCIS (Netherlands)

    Stefánsdóttir, G.

    2012-01-01

    Safety surveillance is important during the entire life cycle of a drug. Pre-marketing trials have been shown to be ineffective in establishing the full safety profile of the drug, mainly due to their relatively small sample size and characteristics of the patients, which are usually younger and

  18. Licensing procedures and safety criteria for research reactors in France

    International Nuclear Information System (INIS)

    Berry, J.L.; Lerouge, B.

    1980-11-01

    This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. Some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors. At the end, a few considerations are given to the consequences of the Osiris core conversion

  19. 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

  20. Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    1997-01-01

    In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

  1. Applications of instrumental neutron activation analysis in the Analytical Division of the Research Center Juelich (KFA)

    International Nuclear Information System (INIS)

    Erdtmann, G.

    1991-12-01

    The Radioanalytical Chemistry Section, as a part of the Central Division of Chemical Analysis of the Research Center KFA Juelich, has the task to provide and to apply nuclear methods in the analytical service for the institutes and projects of the KFA and to customers outside. A great part of this service is trace element determinations by neutron activation analysis using the research reactor FRJ-2. The procedure for the instrumental technique is described and mainly practical aspects are reported in detail. It is based on the k 0 -method developed by Simonits and DeCorte. The results are calculated from the peak areas of the γ-lines and the corresponding k 0 -factors. A new variant of this procedure is required, if the program used for the deconvolution of the γ-spectra provides absolute decay rates of the radionuclides instead of the γ-emission rates. This variant is also described. Some examples of analyses carried out in the analytical service are presented and discussed mainly with respect to accuracy of the results and detection limits. (orig.) [de

  2. Analysis of cancer mortality risk among workers of a research uranium metallurgy division in France

    International Nuclear Information System (INIS)

    Jejati, H.; Laurier, D.; Tirmarche, M.; Giraud, J.M.

    1997-01-01

    This cohort study has been undertaken in response to a suspected cluster of cancers mentioned by workers involved in research activities concerning the metallurgy of uranium. The studied population included all persons having worked between 1950 and 1968 at the Metallurgy Division of the French Atomic Energy Commission (CEA). Exposures were registered on an individual annual basis. For analysis, they were grouped in three categories: use of chemicals agents (Benzene, beryllium, alcohols, solvents ...), manipulation of radioactive materials (uranium, thorium, fission decay products), and exposure to external radiation. This relatively small cohort included 356 workers followed up to December 1990. Out of observed deaths, 21 were from cancer. Total mortality from cancer was less than expected from national rates (Standardised Mortality Ratio = 0.73). Cancer mortality did not increase with duration of exposure to external radiation or with duration of manipulation of radioactive materials. Risk of cancer was increasing with the number of years of exposure to chemicals. The small size of this cohort limits the conclusion of the observed results. The purpose, despite this lack of power, was to answer a worry of the workers, more than to estimate a clear dose-response relationship linked to a specific cancer site. The effect studied here is ''all cancers'', a distinction of the different sites being uninformative because of the very small number of cases observed. Nevertheless, this study suggests some routes for further research: it highlights the importance of considering concomitant exposures like chemical ones in studies of nuclear workers. (author)

  3. Development of Safety Review Guidance for Research and Training Reactors

    International Nuclear Information System (INIS)

    Oh, Kju-Myeng; Shin, Dae-Soo; Ahn, Sang-Kyu; Lee, Hoon-Joo

    2007-01-01

    The KINS already issued the safety review guidance for pressurized LWRs. But the safety review guidance for research and training reactors were not developed. So, the technical standard including safety review guidance for domestic research and training reactors has been applied mutates mutandis to those of nuclear power plants. It is often difficult for the staff to effectively perform the safety review of applications for the permit by the licensee, based on peculiar safety review guidance. The NRC and NSC provide the safety review guidance for test and research reactors and European countries refer to IAEA safety requirements and guides. The safety review guide (SRG) of research and training reactors was developed considering descriptions of the NUREG- 1537 Part 2, previous experiences of safety review and domestic regulations for related facilities. This study provided the safety review guidance for research and training reactors and surveyed the difference of major acceptance criteria or characteristics between the SRG of pressurized light water reactor and research and training reactors

  4. Keeping nurse researchers safe: workplace health and safety issues.

    Science.gov (United States)

    Barr, Jennieffer; Welch, Anthony

    2012-07-01

    This article is a report of a qualitative study of workplace health and safety issues in nursing research. Researcher health and safety have become increasing concerns as there is an increased amount of research undertaken in the community and yet there is a lack of appropriate guidelines on how to keep researchers safe when undertaking fieldwork. This study employed a descriptive qualitative approach, using different sources of data to find any references to researcher health and safety issues. A simple descriptive approach to inquiry was used for this study. Three approaches to data collection were used: interviews with 15 researchers, audits of 18 ethics applications, and exploration of the literature between 1992 and 2010 for examples of researcher safety issues. Data analysis from the three approaches identified participant comments, narrative descriptions or statements focused on researcher health and safety. Nurse researchers' health and safety may be at risk when conducting research in the community. Particular concern involves conducting sensitive research where researchers are physically at risk of being harmed, or being exposed to the development of somatic symptoms. Nurse researchers may perceive the level of risk of harm as lower than the actual or potential harm present in research. Nurse researchers do not consistently implement risk assessment before and during research. Researcher health and safety should be carefully considered at all stages of the research process. Research focusing on sensitive data and vulnerable populations need to consider risk minimization through strategies such as appropriate researcher preparation, safety during data collection, and debriefing if required. © 2012 Blackwell Publishing Ltd.

  5. Los Alamos Life Sciences Division's biomedical and environmental research programs. Progress report, January-December 1980

    Energy Technology Data Exchange (ETDEWEB)

    Holland, L.M.; Stafford, C.G.; Bolen, S.K. (comps.)

    1981-09-01

    Highlights of research progress accomplished in the Life Sciences Division during the year ending December 1980 are summarized. Reports from the following groups are included: Toxicology, Biophysics, Genetics; Environmental Pathology, Organic Chemistry, and Environmental Sciences. Individual abstracts have been prepared for 46 items for inclusion in the Energy Data Base. (RJC)

  6. Research and development activities of the High Pressure Physics Division for the period March 1991-September 1993

    International Nuclear Information System (INIS)

    Godwal, B.K.; Bhadauria, Y.S.

    1993-01-01

    The research and development activities of the High Pressure Physics Division during the period March 1991 to September 1993 are reported in the form of abstracts and titles of the publications. The report is organised into two sections: (A) High Pressure Physics Section, and (B) Seismology Section. A list of staff members of the two sections is also given. (author)

  7. Report style guide for subcontractors of the Efficiency and Renewables Research Section, Energy Division, Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Stone, T.A.; Bennett, M.N.

    1992-09-01

    This document has been paraphrased from the ORNL Document Preparation Guide (DPG). It is intended for use by Efficiency and Renewables Research Section, Energy Division, ORNL subcontractor reports so that review and editing effort can be minimized. Topics covered are typing instructions, document format, usage, abbreviations and acronyms, and standard editing marks.

  8. Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

    International Nuclear Information System (INIS)

    2012-01-01

    This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

  9. Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-15

    This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

  10. Medical Sciences Division report for 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This year`s Medical Sciences Division (MSD) Report is organized to show how programs in our division contribute to the core competencies of Oak Ridge Institute for Science and Education (ORISE). ORISE`s core competencies in education and training, environmental and safety evaluation and analysis, occupational and environmental health, and enabling research support the overall mission of the US Department of Energy (DOE).

  11. Progress report on safety research of high-level waste management for the period April 1986 to March 1987

    International Nuclear Information System (INIS)

    Nakamura, Haruto; Tashiro, Shingo

    1987-08-01

    Researches on high-level waste management at the High Level Waste Management Laboratory and the Waste Safety Testing Facility Operation Division of the Japan Atomic Energy Research Institute in the fiscal year of 1986 are reviewed in the report. Topics in the three sections are as follows: 1) Non-radioactive research has been continued on Synroc irradiation and modellings of waste form leaching. 2) Research results are described in the section of Safety Evaluation for Geological Disposal on engineered barriers, field tests, safety assessment models, migration, natural analogue, seabed disposal and conceptual design of a repository. 3) Adsorption behaviour of plutonium on leach-containers and migration of leached cesium in a rock column are described in the section of Safety Examination of Vitrified Forms in the Hot Cells of WASTEF. (author)

  12. Research reactor safety - an overview of crucial aspects

    International Nuclear Information System (INIS)

    Laverie, M.

    1998-01-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  13. Research reactor safety - an overview of crucial aspects

    Energy Technology Data Exchange (ETDEWEB)

    Laverie, M. [Atomic Energy Commission, Saclay, F-91191 Gif sur Yvette (France)

    1998-07-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  14. Russian Minatom nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    Royen, J.

    1999-01-01

    An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

  15. Criticality safety research on nuclear fuel cycle facility

    Energy Technology Data Exchange (ETDEWEB)

    Miyoshi, Yoshinori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2004-07-01

    This paper present d s current status and future program of the criticality safety research on nuclear fuel cycle made by Japan Atomic Energy Research Institute. Experimental research on solution fuel treated in reprocessing plant has been performed using two critical facilities, STACY and TRACY. Fundamental data of static and transient characteristics are accumulated for validation of criticality safety codes. Subcritical measurements are also made for developing a monitoring system for criticality safety. Criticality safety codes system for solution and power system, and evaluation method related to burnup credit are developed. (author)

  16. Long-term safety of left renal vein division and ligation to expedite complex abdominal aortic surgery.

    Science.gov (United States)

    Samson, Russell H; Lepore, Michael R; Showalter, David P; Nair, Deepak G; Lanoue, Julien B

    2009-09-01

    Left renal vein division and ligation (LRVDAL) is performed to facilitate complex abdominal aortic surgery. Surgeons restore continuity of the vein due to concern that ligation could cause renal compromise or hematuria. However, we report the short and long-term safety of left renal vein division and ligation. Between 1992 and 2007, we divided the left renal vein in 56 patients (40 males, 16 females) ages 57 to 84 (average 74-years-old) who were treated for aortic occlusive disease (9) or abdominal aortic aneurysm (47). Patients requiring concomitant renal artery reconstruction were excluded from this review. Suprarenal cross-clamp was used in 51 patients with temporary vessel-loop control of the renal arteries. Creatinine (Cr) and glomerular filtration rates (eGFR) were measured pre-, post-, and long-term after surgery. Outpatient records of all patients that had survived more than 12 months were also reviewed in order to evaluate the late effects on renal function or symptoms possibly related to LRVDAL. Median procedure duration was 157 (61-375) minutes. Median cross-clamp time was 16 (10-45) minutes. Median intensive care unit (ICU) and hospital length of stays were 2 (1-11) days and 7 (4-58) days, respectively. There were no deaths. There were no complications directly related to renal vein ligation. Hematuria, seen in 2 patients, was a result of traumatic insertion of a Foley catheter. Median pre-op and discharge Cr levels were 1.1 mg/dL (0.7-2.4 mg/dL) and 1.1 mg/dL (0.6-2.1 mg/dL), respectively (P 2.0 mg/dL remained unchanged post-op. Only 2 patients with a Cr of 2.0 mg/dL and both returned to normal by day 3 post-op. Thirty-six patients have been followed for more than a year (median 34.5 months, maximum 144 months) and Cr has remained stable in all but 2 patients. These 2 patients, both with a pre-op Cr of 1.5 mg/dL, subsequently developed Cr levels of 2.1 mg/dL and 2.4 mg/dL but maintained baseline Cr levels for 25 and 34 months, respectively, before

  17. Safety research for evolutionary light water reactors

    International Nuclear Information System (INIS)

    Cacuci, D.G.

    1996-01-01

    The development of nuclear energy has been characterized by a continuous evolution of the technological and philosophical underpinnings of reactor safety to enable operation of the plant without causing harm to either the plant operators or the public. Currently, the safety of a nuclear plant is assured through the combined use of procedures and engineered safety features together with a system of multiple protective barriers against the release of radioactivity. This approach is embodied in the concept of Design-Basis Accidents (DBA), which requires the designers to demonstrate that all credible accidents have been identified and that all safety equipment and procedures perform their functions extremely reliably. Particularly important functions are the automatic protection to shut the reactor down and to remove the decay heat while ensuring the integrity of the containment structure. Within the DBA concept, the so-called severe accidents were conveniently defined to be those accidents that lie beyond the DBA envelope; hence, they did not form part of the safety case. (author)

  18. Safety research for evolutionary light water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Cacuci, D G [Karlsruhe Univ. (T.H.) (Germany). Universitaetsbibliothek

    1996-12-01

    The development of nuclear energy has been characterized by a continuous evolution of the technological and philosophical underpinnings of reactor safety to enable operation of the plant without causing harm to either the plant operators or the public. Currently, the safety of a nuclear plant is assured through the combined use of procedures and engineered safety features together with a system of multiple protective barriers against the release of radioactivity. This approach is embodied in the concept of Design-Basis Accidents (DBA), which requires the designers to demonstrate that all credible accidents have been identified and that all safety equipment and procedures perform their functions extremely reliably. Particularly important functions are the automatic protection to shut the reactor down and to remove the decay heat while ensuring the integrity of the containment structure. Within the DBA concept, the so-called severe accidents were conveniently defined to be those accidents that lie beyond the DBA envelope; hence, they did not form part of the safety case. (author).

  19. An Update on the NASA Planetary Science Division Research and Analysis Program

    Science.gov (United States)

    Richey, Christina; Bernstein, Max; Rall, Jonathan

    2015-01-01

    Introduction: NASA's Planetary Science Division (PSD) solicits its Research and Analysis (R&A) programs each year in Research Opportunities in Space and Earth Sciences (ROSES). Beginning with the 2014 ROSES solicitation, PSD will be changing the structure of the program elements under which the majority of planetary science R&A is done. Major changes include the creation of five core research program elements aligned with PSD's strategic science questions, the introduction of several new R&A opportunities, new submission requirements, and a new timeline for proposal submissionROSES and NSPIRES: ROSES contains the research announcements for all of SMD. Submission of ROSES proposals is done electronically via NSPIRES: http://nspires.nasaprs.com. We will present further details on the proposal submission process to help guide younger scientists. Statistical trends, including the average award size within the PSD programs, selections rates, and lessons learned, will be presented. Information on new programs will also be presented, if available.Review Process and Volunteering: The SARA website (http://sara.nasa.gov) contains information on all ROSES solicitations. There is an email address (SARA@nasa.gov) for inquiries and an area for volunteer reviewers to sign up. The peer review process is based on Scientific/Technical Merit, Relevance, and Level of Effort, and will be detailed within this presentation.ROSES 2014 submission changes: All PSD programs will use a two-step proposal submission process. A Step-1 proposal is required and must be submitted electronically by the Step-1 due date. The Step-1 proposal should include a description of the science goals and objectives to be addressed by the proposal, a brief description of the methodology to be used to address the science goals and objectives, and the relevance of the proposed research to the call submitted to.Additional Information: Additional details will be provided on the Cassini Data Analysis Program, the

  20. Safety considerations of new critical assembly for the Research Reactor Institute, Kyoto University

    International Nuclear Information System (INIS)

    Umeda, Iwao; Matsuoka, Naomi; Harada, Yoshihiko; Miyamoto, Keiji; Kanazawa, Takashi

    1975-01-01

    The new critical assembly type of nuclear reactor having three cores for the first time in the world was completed successfully at the Research Reactor Institute of Kyoto University in autumn of 1974. It is called KUCA (Kyoto University Critical Assembly). Safety of the critical assembly was considered sufficiently in consequence of discussions between the researchers of the institute and the design group of our company, and then many bright ideas were created through the discussions. This paper is described the new safety design of main equipments - oil pressure type center core drive mechanism, removable water overflow mechanism, core division mechanism, control rod drive mechansim, protection instrumentation system and interlock key system - for the critical assembly. (author)

  1. Researches on nuclear criticality safety evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-10-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  2. Researches on nuclear criticality safety evaluation

    International Nuclear Information System (INIS)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi

    2003-01-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  3. Research and exploration on nuclear safety culture construction

    International Nuclear Information System (INIS)

    Zhang Lifang; Zhao Hongtao; Wang Hongwei

    2012-01-01

    This thesis mainly researched the definition, characteristics, development stage and setup procedure concerning nuclear safety culture, based on practice and experiences in Technical Physics Institute of Heilongjian. Academy of Science. The author discussed the importance of nuclear safety culture construction for an enterprise of nuclear technology utilization, and emphasized all the enterprise and individual who engaged in nuclear and radiation safety should acquire good nuclear safety culture quality, and ensure the application and development of the nuclear safety cult.ure construction in the enterprises of nu- clear technological utilization. (authors)

  4. Theoretical Division annual report, FY 1975

    International Nuclear Information System (INIS)

    Carruthers, P.A.

    1976-02-01

    This report presents an overview of the activities in the Theoretical Division and a summary of research highlights during FY 1975. It is intended to inform a wide audience about the theoretical work of the LASL and, therefore, contains introductory material which places recent advances in a broader context. The report is organized into two special interest reports: reactor safety research and the Advanced Research Committee, and 11 reports from the T-Division group leaders on the work of their respective groups. Main interests and responsibilities are outlined including the relationship of the group's work to the work of other T-Division groups and other divisions at the Laboratory. The description of research highlights for FY 1975 explains in a fairly simple, straightforward manner the major recent advances and their significance. Each group report is followed by a publication list for FY 1975 (330 references) and a list of talks given outside the Laboratory (140 references). 29 figures

  5. Anthropology in Agricultural Health and Safety Research and Intervention.

    Science.gov (United States)

    Arcury, Thomas

    2017-01-01

    Agriculture remains a dangerous industry, even as agricultural science and technology continue to advance. Research that goes beyond technological changes to address safety culture and policy are needed to improve health and safety in agriculture. In this commentary, I consider the potential for anthropology to contribute to agricultural health and safety research by addressing three aims: (1) I briefly consider what the articles in this issue of the Journal of Agromedicine say about anthropologists in agricultural health and safety; (2) I discuss what anthropologists can add to agricultural health and safety research; and (3) I examine ways in which anthropologists can participate in agricultural health and safety research. In using their traditions of rigorous field research to understand how those working in agriculture perceive and interpret factors affecting occupational health and safety (their "emic" perspective), and translating this perspective to improve the understanding of occupational health professionals and policy makers (an "etic" perspective), anthropologists can expose myths that limit improvements in agricultural health and safety. Addressing significant questions, working with the most vulnerable agricultural communities, and being outside establishment agriculture provide anthropologists with the opportunity to improve health and safety policy and regulation in agriculture.

  6. Progress Report for the Chemical and Energy Research Section of the Chemical Technology Division: July-December 1998

    Energy Technology Data Exchange (ETDEWEB)

    Jubin, R.T.

    1999-06-01

    This report summarizes the major activities conducted in the Chemical and Energy Research Section of the Chemical Technology Division at Oak Ridge National Laboratory (ORNL) during the period July-December 1998. The section conducts basic and applied research and development in chemical engineering, applied chemistry, and bioprocessing, with an emphasis on energy-driven technologies and advanced chemical separations for nuclear and waste applications.

  7. Quarterly Progress Report for the Chemical and Energy Research Section of the Chemical Technology Division: April-June 1998

    Energy Technology Data Exchange (ETDEWEB)

    Jubin, R.T.

    1999-04-01

    This report summarizes the major activities conducted in the Chemical and Energy Research Section of the Chemical Technology Division at Oak Ridge National Laboratory (ORNL) during th eperiod April-June 1998. The section conducts basic and applied research and development in chemical engineering, applied chemistry, and bioprocessing, with an emphasis on energy-driven technologies and advanced chemical separations for nuclear and waste applications.

  8. Safety relevance of vision research and theory.

    NARCIS (Netherlands)

    Koornstra, M.J.

    1993-01-01

    This article discusses the importance of drivers' visual perception to road safety. Evidence is provided to show that the visual perception of a person who is moving at high speed can be seriously affected by both poor visibility and defective eyesight. The point is made that the human eye and mind

  9. 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)

  10. Improving nuclear safety at international research reactors: The Integrated Research Reactor Safety Enhancement Program (IRRSEP)

    International Nuclear Information System (INIS)

    Huizenga, David; Newton, Douglas; Connery, Joyce

    2002-01-01

    Nuclear energy continues to play a major role in the world's energy economy. Research and test reactors are an important component of a nation's nuclear power infrastructure as they provide training, experiments and operating experience vital to developing and sustaining the industry. Indeed, nations with aspirations for nuclear power development usually begin their programs with a research reactor program. Research reactors also are vital to international science and technology development. It is important to keep them safe from both accident and sabotage, not only because of our obligation to prevent human and environmental consequence but also to prevent corresponding damage to science and industry. For example, an incident at a research reactor could cause a political and public backlash that would do irreparable harm to national nuclear programs. Following the accidents at Three Mile Island and Chernobyl, considerable efforts and resources were committed to improving the safety posture of the world's nuclear power plants. Unsafe operation of research reactors will have an amplifying effect throughout a country or region's entire nuclear programs due to political, economic and nuclear infrastructure consequences. (author)

  11. Quarterly Progress Report for the Chemical and Energy Research Section of the Chemical Technology Division: January-March 1998

    Energy Technology Data Exchange (ETDEWEB)

    Jubin, R.T.

    1999-03-01

    This report summarizes the major activities conducted in the Chemical and Energy Research Section of the Chemical Technology Division at Oak Ridge National Laboratory (ORNL) during the period January-March 1998. The section conducts basic and applied research and development in chemical engineering, applied chemistry, and bioprocessing, with an emphasis on energy driven technologies and advanced chemical separations for nuclear and waste applications. The report describes the various tasks performed within nine major areas of research: Hot Cell Operations, Process Chemistry and Thermodynamics, Molten Salt Reactor Experiment (MSRE) Remediation Studies, Chemistry Research, Biotechnology, Separations and Materials Synthesis, Fluid Structure and Properties, Biotechnology Research, and Molecular Studies.

  12. Reactor Safety Research: Semiannual report, July-December 1986

    Energy Technology Data Exchange (ETDEWEB)

    1987-11-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of the accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance and behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the tehcnology base supporting licensing decisions.

  13. Reactor Safety Research: Semiannual report, July-December 1986

    International Nuclear Information System (INIS)

    1987-11-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of the accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance and behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the tehcnology base supporting licensing decisions

  14. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    1999-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  15. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  16. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  17. Nuclear power reactor safety research activities in CIAE

    International Nuclear Information System (INIS)

    Pu Shendi; Huang Yucai; Xu Hanming; Zhang Zhongyue

    1994-01-01

    The power reactor safety research activities in CIAE are briefly reviewed. The research work performed in 1980's and 1990's is mainly emphasised, which is closely related to the design, construction and licensing review of Qinshan Nuclear Power Plant and the safety review of Guangdong Nuclear Power Station. Major achievements in the area of thermohydraulics, nuclear fuel, probabilistic safety assessment and severe accident researches are summarized. The foreseeable research plan for the near future, relating to the design and construction of 600 MWe PWR NPP at Qinshan Site (phase II development) is outlined

  18. Buff book 1: status summary report, water reactor safety research

    International Nuclear Information System (INIS)

    1980-01-01

    This Management Report, to provide information for monitoring and controlling the progress of LWR Safety Research Projects Associated with the Office of Nuclear Regulatory Research and other agencies and organizations engaged in nuclear safety research. It utilizes data pertaining to project schedules, cost, and status which have been integrated into a network-based management information system, The purpose of this publication is to provide a vehicle for review of the current status and overall progress of the safety Research Program from a managerial point of view

  19. 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.)

  20. 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.)

  1. 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.

  2. 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.

  3. Accelerator and Fusion Research Division annual report, October 1980-September 1981. Fiscal year, 1981

    International Nuclear Information System (INIS)

    Johnson, R.K.; Thomson, H.A.

    1982-04-01

    Major accomplishments during fiscal year 1981 are presented. During the Laboratory's 50th anniversary celebrations, AFRD and the Nuclear Science Division formally dedicated the new (third) SuperHILAC injector that adds ions as heavy as uranium to the ion repertoire at LBL's national accelerator facilities. The Bevalac's new multiparticle detectors (the Heavy Ion Spectrometer System and the GSI-LBL Plastic Ball/Plastic Wall) were completed in time to take data before the mid-year shutdown to install the new vacuum liner, which passed a milestone in-place test with flying colors in September. The Bevalac biomedical program continued patient treatment with neon beams aimed at establishing a complete data base for a dedicated biomedical accelerator, the design of which NCI funded during the year. Our program to develop alternative Isabelle superconducting dipole magnets, which DOE initiated in FY80, proved the worth of a new magnet construction technique and set a world record - 7.6 Tesla at 1.8 K - with a model magnet in our upgraded test facility. Final test results at LBL were obtained by the Magnetic Fusion Energy Group on the powerful neutral beam injectors developed for Princeton's TFTR. The devices exceeded the original design requirements, thereby completing the six-year, multi-million-dollar NBSTF effort. The group also demonstrated the feasibility of efficient negative-ion-based neutral beam plasma heating for the future by generating 1 A of negative ions at 34 kV for 7 seconds using a newly developed source. Collaborations with other research centers continued, including: (1) the design of LBL/Exxon-dedicated beam lines for the Stanford Synchrotron Radiation Laboratory; (2) beam cooling tests at Fermilab and the design of a beam cooling system for a proton-antiproton facility there; and (3) the development of a high-current betatron for possible application to a free electron laser

  4. Safety in decommissioning of research reactors

    International Nuclear Information System (INIS)

    1986-01-01

    This Guide covers the technical and administrative considerations relevant to the nuclear aspects of safety in the decommissioning of reactors, as they apply to the reactor and the reactor site. While the treatment, transport and disposal of radioactive wastes arising from decommissioning are important considerations, these aspects are not specifically covered in this Guide. Likewise, other possible issues in decommissioning (e.g. land use and other environmental issues, industrial safety, financial assurance) which are not directly related to radiological safety are also not considered. Generally, decommissioning will be undertaken after planned final shutdown of the reactor. In some cases a reactor may have to be decommissioned following an unplanned or unexpected event of a series or damaging nature occurring during operation. In these cases special procedures for decommissioning may need to be developed, peculiar to the particular circumstances. This Guide could be used as a basis for the development of these procedures although specific consideration of the circumstances which create the need for them is beyond its scope

  5. Twenty-five years of research in hydro-ecology at the EDF research and development division

    International Nuclear Information System (INIS)

    Gosse, Ph.

    1999-01-01

    Hydro-ecology (or aquatic ecology) is the study of aquatic systems in their interacting aspects: physical, chemical and biological. The creation in 1974 of the Environment Department at EDF Research and Development Division marked the start in France of quantitative hydro-ecology applied to power generation installations. The studies developed around several main themes, determined both the expansion of the nuclear programme and by changes in French environmental regulations, in particular the 1976 law on impact studies, the 1984 fishing and hydro-biology law and the 1992 water law. In this framework, he effect of artificial warming of rivers, eutrophication of continental and marine waters, transfers of mineral micro-pollutants and radionuclides in rivers, and problems specific to hydropower installations such as guaranteed in stream flow or fish pass design, have been studies. This work, conducted in collaboration with many other laboratories, has led to the development of original quantitative approaches, notably in the field of numerical modelling. The paper selects several of the tools developed whose scope of application is wider than the environment and management of thermal or hydropower plants. Two major applications grouping the experience acquired in hydro-ecology are presented: the AGIRE software and the global environment study of the Singrauli area in India. (author)

  6. Organisation of safety research programmes and infrastructure for existing reactors

    International Nuclear Information System (INIS)

    Micaelli, J.C.

    2008-01-01

    The author reviewed the main drivers of safety research, noting that challenging research is an excellent means to preserve know-how and professional skills. International efforts such the NEA-CSNI joint projects are an efficient means to support experimental infrastructure for safety research, while providing useful experimental results. Other initiatives, e.g. within the EU, aimed at developing networks of international expertise and infrastructure were also mentioned. (author)

  7. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  8. 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

  9. Nirex safety assessment research programme: 1987/88

    International Nuclear Information System (INIS)

    George, D.; Hodgkinson, D.P.

    1987-01-01

    The Nirex Safety Assessment Research programme's objective is to provide information for the radiological safety case for disposing low-level and intermediate-level radioactive wastes in underground repositories. The programme covers a wide range of experimental studies and mathematical modelling for the near and far field. It attempts to develop a quantitative understanding of events and processes which have an impact on the safety of radioactive waste disposal. (U.K.)

  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. Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

    1998-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

  12. IRSN safety research carried out for reviewing geological disposal safety case

    International Nuclear Information System (INIS)

    Serres, Christophe; Besnus, Francois; Gay, Didier

    2010-01-01

    The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

  13. Research reactors: design, safety requirements and applications

    International Nuclear Information System (INIS)

    Hassan, Abobaker Mohammed Rahmtalla

    2014-09-01

    There are two types of reactors: research reactors or power reactors. The difference between the research reactor and energy reactor is that the research reactor has working temperature and fuel less than the power reactor. The research reactors cooling uses light or heavy water and also research reactors need reflector of graphite or beryllium to reduce the loss of neutrons from the reactor core. Research reactors are used for research training as well as testing of materials and the production of radioisotopes for medical uses and for industrial application. The difference is also that the research reactor smaller in terms of capacity than that of power plant. Research reactors produce radioactive isotopes are not used for energy production, the power plant generates electrical energy. In the world there are more than 284 reactor research in 56 countries, operates as source of neutron for scientific research. Among the incidents related to nuclear reactors leak radiation partial reactor which took place in three mile island nuclear near pennsylvania in 1979, due to result of the loss of control of the fission reaction, which led to the explosion emitting hug amounts of radiation. However, there was control of radiation inside the building, and so no occurred then, another accident that lead to radiation leakage similar in nuclear power plant Chernobyl in Russia in 1986, has led to deaths of 4000 people and exposing hundreds of thousands to radiation, and can continue to be effect of harmful radiation to affect future generations. (author)

  14. High Burnup Fuel Performance and Safety Research

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Je Keun; Lee, Chan Bok; Kim, Dae Ho (and others)

    2007-03-15

    The worldwide trend of nuclear fuel development is to develop a high burnup and high performance nuclear fuel with high economies and safety. Because the fuel performance evaluation code, INFRA, has a patent, and the superiority for prediction of fuel performance was proven through the IAEA CRP FUMEX-II program, the INFRA code can be utilized with commercial purpose in the industry. The INFRA code was provided and utilized usefully in the universities and relevant institutes domesticallly and it has been used as a reference code in the industry for the development of the intrinsic fuel rod design code.

  15. Progress report concerning safety research for nuclear reactor facilities

    International Nuclear Information System (INIS)

    1978-01-01

    Examination and evaluation of safety research results for nuclear reactor facilities have been performed, as more than a year has elapsed since the plan had been initiated in April, 1976, by the special sub-committee for the safety of nuclear reactor facilities. The research is carried out by being divided roughly into 7 items, and seems to be steadily proceeding, though it does not yet reach the target. The above 7 items include researches for (1) criticality accident, (2) loss of coolant accident, (3) safety for light water reactor fuel, (4) construction safety for reactor facilities, (5) reduction of release of radioactive material, (6) safety evaluation based on the probability theory for reactor facilities, and (7) aseismatic measures for reactor facilities. With discussions on the progress and the results of the research this time, research on the behaviour on fuel in abnormal transients including in-core and out-core experiments has been added to the third item, deleting the power-cooling mismatch experiment in Nuclear Safety Research Reactor of JAERI. Also it has been decided to add two research to the seventh item, namely measured data collection, classification and analysis, and probability assessment of failures due to an earthquake. For these 7 items, the report describes the concrete contents of research to be performed in fiscal years of 1977 and 1978, by discussing on most rational and suitable contents conceivable at present. (Wakatsuki, Y.)

  16. Division of Biological and Medical Research annual report, 1979. [Lead abstract

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.W. (ed.)

    1979-01-01

    Separate abstracts were prepared for 14 of the 20 sections included in this progress report. The other 6 sections include: introductory statements by the division director; descriptions of the animal, computer, electron microscope, and radiation support facilities; a listing of the educational activities, divisional seminars, and oral presentations by staff members; and divisional staff publications. An author index to the report is included. (ERB)

  17. Safety research needs for Russian-designed reactors. Requirements situation

    International Nuclear Information System (INIS)

    Brown, R. Allan; Holmstrom, Heikki; Reocreux, Michel; Schulz, Helmut; Liesch, Klaus; Santarossa, Giampiero; Hayamizu, Yoshitaka; Asmolov, Vladimir; Bolshov, Leonid; Strizhov, Valerii; Bougaenko, Sergei; Nikitin, Yuri N.; Proklov, Vladimir; Potapov, Alexandre; Kinnersly, Stephen R.; Voronin, Leonid M.; Honekamp, John R.; Frescura, Gianni M.; Maki, Nobuo; Reig, Javier; ); Bekjord, Eric S.; Rosinger, Herbert E.

    1998-01-01

    In June 1995, an OECD Support Group was set up to perform a broad study of the safety research needs of Russian-designed reactors. The emphasis of the study is on the VVER-type reactors in part because of the larger base of knowledge within the NEA Member countries related to LWRs. For the RBMKs, the study does not make the judgement that such reactors can be brought to acceptable levels of safety but focuses on near term efforts that can contribute to reducing the risk to the public. The need for the safety research must be evaluated in context of the lifetime of the reactors. The principal outcome of the work of the Support Group is the identification of a number of research topics which the members believe should receive priority attention over the next several years if risk levels are to be reduced and public safety enhanced. These appear in the Conclusions and Recommendations section of the report, and are the following: - The most important near-term need for VVER and RBMK safety research is to establish a sound technical basis for the emergency operating procedures used by the plant staff to prevent or halt the progression of accidents (i.e., Accident Management) and for plant safety improvements. - Co-operation of Western and Eastern experts should help to avoid East-West know-how gaps in the future, as safety technology continues to improve. - Safety research in Eastern countries will make an important contribution to public safety as it has in OECD countries. - RBMK safety research, including verification of codes, starts from a smaller base of experience than VVER, and is at an earlier stage of development. Technical Conclusions: - Research to improve human performance and operational safety of VVER and RBMK plants is extremely important. - VVER thermal-hydraulic and reactor physics research should focus on full validation of codes to VVER-specific features, and on extension of experimental data base. - Methods of assessing VVER pressure boundary

  18. Safety regulations concerning instrumentation and control systems for research reactors

    International Nuclear Information System (INIS)

    El-Shanshoury, A.I.

    2009-01-01

    A brief study on the safety and reliability issues related to instrumentation and control systems in nuclear reactor plants is performed. In response, technical and strategic issues are used to accomplish instrumentation and control systems safety. For technical issues there are ; systems aspects of digital I and C technology, software quality assurance, common-mode software, failure potential, safety and reliability assessment methods, and human factors and human machine interfaces. The strategic issues are the case-by-case licensing process and the adequacy of the technical infrastructure. The purpose of this work was to review the reliability of the safety systems related to these technical issues for research reactors

  19. Radiological safety design considerations for fusion research experiments

    International Nuclear Information System (INIS)

    Crase, K.W.; Singh, M.S.

    1979-01-01

    A wide variety of fusion research experiments are in the planning or construction stages. Two such experiments, the Nova Laser Fusion Facility and the Mirror Fusion Test Facility (MFTF), are currently under construction at Lawrence Livermore Laboratory. Although the plasma chamber vault for MFTF and the Nova target room will have thick concrete walls and roofs, the radiation safety problems are made complex by the numerous requirements for shield wall penetrations. This paper addresses radiation safety considerations for the MFTF and Nova experiments, and the need for integrated safety considerations and safety technology development during the planning stages of fusion experiments

  20. Argonne National Laboratory, High Energy Physics Division: Semiannual report of research activities, July 1, 1986-December 31, 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This paper discusses the research activity of the High Energy Physics Division at the Argonne National Laboratory for the period, July 1986-December 1986. Some of the topics included in this report are: high resolution spectrometers, computational physics, spin physics, string theories, lattice gauge theory, proton decay, symmetry breaking, heavy flavor production, massive lepton pair production, collider physics, field theories, proton sources, and facility development

  1. NAS Human Factors Safety Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — This laboratory conducts an integrated program of research on the relationship of factors concerning individuals, work groups, and organizations as employees perform...

  2. Emerging research methods and their application to road safety.

    Science.gov (United States)

    Tarko, Andrew; Boyle, Linda Ng; Montella, Alfonso

    2013-12-01

    The study of road safety has seen great strides over the past few decades with advances in analytical methods and research tools that allow researchers to provide insights into the complex interactions of the driver, vehicle, and roadway. Data collection methods range from traditional traffic and roadway sensors to instrumented vehicles and driving simulators, capable of providing detailed data on both the normal driving conditions and the circumstances surrounding a safety critical event. In September 2011, the Third International Conference on Road Safety and Simulation was held in Indianapolis, Indiana, USA, which was hosted by the Purdue University Center for Road Safety and sponsored by the Transportation Research Board and its three committees: ANB20 Safety Data, Analysis and Evaluation, AND30 Simulation and Measurement of Vehicle and Operator Performance, and ABJ95 Visualization in Transportation. The conference brought together two hundred researchers from all over the world demonstrating some of the latest research methods to quantify crash causality and associations, and model road safety. This special issue is a collection of 14 papers that were presented at the conference and then peer-reviewed through this journal. These papers showcase the types of analytical tools needed to examine various crash types, the use of naturalistic and on-road data to validate the use of surrogate measures of safety, and the value of driving simulators to examine high-risk situations. Copyright © 2013 Elsevier Ltd. All rights reserved.

  3. Review of current status of LWR safety research in Japan

    International Nuclear Information System (INIS)

    Yamada, Tasaburo; Mishima, Yoshitsugu; Ando, Yoshio; Miyazono, Shohachiro; Takashima, Yoichi.

    1977-01-01

    The Japan Atomic Energy Commission has exerted efforts on the research of the safety of nuclear plants in Japan, and ''Nuclear plant safety research committees'' was established in August 1974, which is composed of the government and the people. The philosophy of safety research, research and development plan, the forwarding procedure of the plan, international cooperation, for example LOFT program, and the effective feed back of the experimental results concerning nuclear safety are reviewed in this paper at first. As for the safety of nuclear reactors the basic philosophy that radio active fission products are contained in fuel or reactors with multiple barriers, (defence in depth) and almost no fission product is released outside reactor plants even at the time of hypothetical accident, is kept, and the research and development history and the future plan are described in this paper with the related technical problems. The structural safety is also explained, for example, on the philosophy ''leak before break'', pipe rupture, pipe restraint and stress analysis. The release of radioactive gas and liquid is decreased as the philosophy ''ALAP''. And probability safety evaluation method, LOCA, reactivity, accident and aseismatic design in nuclear plants in Japan are described. (Nakai, Y.)

  4. Current and Past Research on Autistic Children and Their Families. Conducted by Division TEACCH (Treatment and Education of Autistic and Related Communication Handicapped Children). TEACCH Research Report.

    Science.gov (United States)

    Schopler, Eric

    This report summarizes research conducted by, or in collaboration with, the Division TEACCH (Treatment and Education of Autistic and related Communication handicapped CHildren) of the Department of Psychiatry in the University of North Carolina School of Medicine at Chapel Hill. The summaries contain bibliographic citations for published papers…

  5. Radiological safety at Argonne National Laboratory's heavy ion research facility

    International Nuclear Information System (INIS)

    Cooke, R.H.; Wynveen, R.A.

    1985-01-01

    This paper discusses the radiological safety system to be employed at the Argonne tandem-linac accelerator system (ATLAS). The design parameters of ATLAS that affect safety have remained unchanged since ATLAS construction began in 1982. This paper will present the details of the hardware, the administrative controls, and the radiation monitoring that will be in effect when beam is produced in April 1985. The experimental hall utilizing the maximum energy beam (proportional27 MeV per nucleon) from the completed ATLAS has been partitioned with shielding blocks into its final configuration. Because scientists want access to some of the partitioned-off areas while beam is present in other areas, an interlock and logic system allowing such occupancy has been designed. The rationale and hardware of the system will be discussed. Since one of the potential radiation hazards is high-energy forward-directed neutrons from any location where the beam impinges (such as collimators, bending and focussing systems, experimental targets, and beam stops), radiation surveys and hazard assessments are necessary for the administrative controls that allow occupancy of various areas. Because of the various uses of ATLAS, neutrons (the dominant beam hazard) will be non-existent in some experiments and will be of energies > or approx.10 MeV for a few experiments. These conditions may exist at specific locations during beam preparation but may change rapidly when beam is finally delivered to an experimental area. Monitoring and assessing such time varying and geographically changing hazards will be a challenge since little data will be available on source terms until various beams are produced of sufficient intensity and energy to make measurements. How the operating division for ATLAS and the Argonne safety division are addressing this aspect through administrative controls will also be discussed. (orig./HSI)

  6. Licensing procedures and safety criteria for research reactors in France

    International Nuclear Information System (INIS)

    Berry, J.L.; Lerouge, B.

    1983-01-01

    From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon

  7. Licensing procedures and safety criteria for research reactors in France

    Energy Technology Data Exchange (ETDEWEB)

    Berry, J L; Lerouge, B [Centre d' Etudes Nucleaires de Saclay (France)

    1983-08-01

    From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon.

  8. NRC safety research in support of regulation, FY 1991

    International Nuclear Information System (INIS)

    1992-04-01

    This report, the seventh in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1991. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  9. NRC safety research in support of regulation, FY 1990

    International Nuclear Information System (INIS)

    1991-04-01

    This report, the sixth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1990. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  10. Water cooled reactor technology: Safety research abstracts no. 1

    International Nuclear Information System (INIS)

    1990-01-01

    The Commission of the European Communities, the International Atomic Energy Agency and the Nuclear Energy Agency of the OECD publish these Nuclear Safety Research Abstracts within the framework of their efforts to enhance the safety of nuclear power plants and to promote the exchange of research information. The abstracts are of nuclear safety related research projects for: pressurized light water cooled and moderated reactors (PWRs); boiling light water cooled and moderated reactors (BWRs); light water cooled and graphite moderated reactors (LWGRs); pressurized heavy water cooled and moderated reactors (PHWRs); gas cooled graphite moderated reactors (GCRs). Abstracts of nuclear safety research projects for fast breeder reactors are published independently by the Nuclear Energy Agency of the OECD and are not included in this joint publication. The intention of the collaborating international organizations is to publish such a document biannually. Work has been undertaken to develop a common computerized system with on-line access to the stored information

  11. NRC safety research in support of regulation--FY 1989

    International Nuclear Information System (INIS)

    1990-04-01

    This report, the fifth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1989. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  12. Radiation safety status at a bio medical research centre

    International Nuclear Information System (INIS)

    Mishra, S.K.

    1998-01-01

    Radioisotopes are being used for biomedical research purpose at School of Life Science, Jawaharlal Nehru University for the last twenty five years. Present paper analyses the overall status of radiation safety at this Centre

  13. NRC safety research in support of regulation, 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This report, the fourth in a series of annual reports, was prepared in response to Congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1988. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  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. The Health and Safety Executive's strategy for nuclear safety research 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This brochure illustrates HSE's nuclear safety research strategy for 1996. It is divided into two parts. The first part presents HSE's overall strategy. The second contains short strategy statements for the individual areas detailed above, providing a rationale and objectives for the particular safety issues in the NRI, where greater detail can be found. (author)

  16. Safety research basic plan of JNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Japan Nuclear Cycle Development Institute (JNC) formally succeeded to Power Reactor and Nuclear Fuel Development Corporation (PNC) on October, 1 1998. This report describes the basic plan for major program of JNC which consists of two parts: management philosophy of the new institute and the latest revised medium term program. In the first part, the primary mission of JNC is to perform its R and D concentrating on fast breeder reactor and its fuel cycle, and treatment and disposal of high-level radioactive wastes, while at the same time giving special consideration to safety. In the second, individual programs in the new basic plan are discussed in detail. The outline and schedule of each program are also attached in the table form. (H. Itami)

  17. Safety of research reactors. Topical issues paper no. 4

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.; Ferraz-Bastos, J.L.; Kim, S.C.; Voth, M.; Boeck, H.; Dimeglio, F.; Litai, D.

    2001-01-01

    Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety review of the research reactor facility and to verify compliance with the IAEA Safety Standards. The methods used during an INSARR mission have been collected and analysed. Some of the important issues identified are the following: general ageing of the facility; uncertain status of many research reactors (in extended shutdown); indefinite deferral of return to operation or decommissioning; inadequate regulatory supervision; insufficient systematic (periodic) reassessment of safety; lack of quality assurance (QA) programmes; lack of an international safety convention or arrangement; lack of financial support for safety measures (e.g. safety reassessment, safety upgrading, decommissioning) and utilization; lack of clear utilization programmes; inadequate emergency preparedness; inadequate safety documentation (e.g. safety analysis report, operating rules and procedures, emergency plan); inadequate funding of shutdown reactors; weak safety culture; loss of expertise and corporate memory; loss of information concerning radioactive materials contained in retired experimental devices stored in the facility indefinitely; obsolescence of equipment and lack of spare parts; inadequate training and qualifications of regulators and operators; safety implications of new fuel types. These issues have been addressed by the IAEA Secretariat and the chairman of the International Nuclear Safety Advisory Group (INSAG). INSAG has identified three major safety issues that are: the increasing age of research reactors, the number of research reactors that are not operating anymore but have not been decommissioned, and the number of research reactors in countries that do not have appropriate regulatory authorities. This issue paper discusses the concerns generated by an analysis of the results of INSARR missions and those expressed by INSAG. The

  18. Safety culture and quality management of Kartini research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Syarip [Yogyakarta Nuclear Research Centre, Yogyakarta (Indonesia); Hauptmanns, Ulrich [Department of Plant Design and Safety, Otto-Von-Guericke-University, Magdeburg (Germany)

    1999-10-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  19. Safety culture and quality management of Kartini research reactor

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, Ulrich

    1999-01-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  20. Knowledge basis in safety culture for researchers and practitioners

    International Nuclear Information System (INIS)

    Vieira Neto, Antonio S.; Barroso, Antonio C.O.; Goncalves, Adriana

    2009-01-01

    This paper presents the main characteristics of the knowledge basis in safety culture which is being developed at the IPEN-CNEN/SP, one of the Brazilian nuclear institutes of research. The main objective of this basis is to organize the information about safety culture found in the literature and to make it available to researchers and practitioners. The first stage of the development of this basis is already finished being the subject of this work. (author)

  1. Research and development program in reactor safety for NUCLEBRAS

    International Nuclear Information System (INIS)

    Pinheiro, R.B.; Resende Lobo, A.A. de; Horta, J.A.L.; Avelar Esteves, F. de; Lepecki, W.P.S.; Mohr, K.; Selvatici, E.

    1984-01-01

    With technical assistance from the IAEA, it was established recently an analytical and experimental Research and Development Program for NUCLEBRAS in the area of reactor safety. The main objectives of this program is to make possible, with low investments, the active participation of NUCLEBRAS in international PWR safety research. The analytical and experimental activities of the program are described with some detail, and the main results achieved up to now are presented. (Author) [pt

  2. Translating Health Services Research into Practice in the Safety Net.

    Science.gov (United States)

    Moore, Susan L; Fischer, Ilana; Havranek, Edward P

    2016-02-01

    To summarize research relating to health services research translation in the safety net through analysis of the literature and case study of a safety net system. Literature review and key informant interviews at an integrated safety net hospital. This paper describes the results of a comprehensive literature review of translational science literature as applied to health care paired with qualitative analysis of five key informant interviews conducted with senior-level management at Denver Health and Hospital Authority. Results from the literature suggest that implementing innovation may be more difficult in the safety net due to multiple factors, including financial and organizational constraints. Results from key informant interviews confirmed the reality of financial barriers to innovation implementation but also implied that factors, including institutional respect for data, organizational attitudes, and leadership support, could compensate for disadvantages. Translating research into practice is of critical importance to safety net providers, which are under increased pressure to improve patient care and satisfaction. Results suggest that translational research done in the safety net can better illuminate the special challenges of this setting; more such research is needed. © Health Research and Educational Trust.

  3. Thermal hydraulic tests for reactor safety system -Research on the improvement of nuclear safety-

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Park, Chun Kyeong; Yang, Seon Kyu; Chung, Chang Hwan; Chun, Shee Yeong; Song, Cheol Hwa; Chun, Hyeong Gil; Chang, Seok Kyu; Chung, Heung Joon; Won, Soon Yeon; Cho, Yeong Ro; Kim, Bok Deuk; Min, Kyeong Ho

    1994-07-01

    The present research aims at the development of the thermal hydraulic verification test technology for the reactor safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. (Author)

  4. Safety research in nuclear fuel cycle at PNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF{sub 6}, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  5. Safety research in nuclear fuel cycle at PNC

    International Nuclear Information System (INIS)

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF 6 , uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  6. Annotated bibliography of Accelerator Technology Division research and development, 1978-1985

    International Nuclear Information System (INIS)

    Jameson, R.A.; Nicol, C.S.; Cochran, M.A.

    1985-09-01

    A bibliography is presented of unclassified published and in-house technical material written by members of the Accelerator Technology Division, Los Alamos National Laboratory, since its inception in January, 1978. The author and subject concordances in this report provide cross-reference to detailed citations kept in a computer database and a microfilm file of the documents. The citations include an abstract and other notes, and can be searched for key words and phrases

  7. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Moon Kee; Park, Choon Kyung; Yang, Sun Kyoo; Chun, Se Yung; Song, Chul Hwa; Jun, Hyung Kil; Jung, Heung Joon; Won, Soon Yun; Cho, Yung Roh; Min, Kyung Hoh; Jung, Jang Hwan; Jang, Suk Kyoo; Kim, Bok Deuk; Kim, Wooi Kyung; Huh, Jin; Kim, Sook Kwan; Moon, Sang Kee; Lee, Sang Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-06-01

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author).

  8. Operating experience feedback from safety significant events at research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Shokr, A.M. [Atomic Energy Authority, Abouzabal (Egypt). Egypt Second Research Reactor; Rao, D. [Bhabha Atomic Research Centre, Mumbai (India)

    2015-05-15

    Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

  9. 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

  10. Safety infrastructure for countries establishing their first research reactor

    International Nuclear Information System (INIS)

    Abou Yehia, H.; Shokr, A.M.

    2010-01-01

    Establishment of a research reactor is a major project requiring careful planning, preparation, implementation, and investment in time and human resources. The implementation of such a project requires establishment of sustainable infrastructures, including legal and regulatory, safety, technical, and economic. An analysis of the needs for a new research reactor facility should be performed including the development of a utilization plan and evaluation of site availability and suitability. All these elements should be covered by a feasibility study of the project. This paper discusses the elements of such a study with the main focus on the specific activities and steps for developing the necessary safety infrastructure. Progressive involvement of the main organizations in the project, and application of the IAEA Code of Conduct on the Safety of Research Reactors and IAEA Safety Standards in different phases of the project are presented and discussed. (author)

  11. Safety research needs for Russian-designed reactors

    International Nuclear Information System (INIS)

    1998-01-01

    In June 1995, an OECD Support Group was set up to perform a broad study of the safety research needs of Russian-designed reactors. This Support Group was endorsed by the CSNI. The Support Group, which is composed of senior experts on safety research from several OECD countries and from Russia, prepared this Report. The Group reviewed the safety research performed to support Russian-designed reactors and set down its views on future needs. The review concentrates on the following main topics: Thermal-Hydraulics/Plant Transients for VVERs; Integrity of Equipment and Structures for VVERs; Severe Accidents for VVERs; Operational Safety Issues; Thermal-Hydraulics/Plant Transients for RBMKs; Integrity of Equipment and Structures for RBMKs; Severe Accidents for RBMKs. (K.A.)

  12. Operating experience feedback from safety significant events at research reactors

    International Nuclear Information System (INIS)

    Shokr, A.M.

    2015-01-01

    Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-04-01

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

  14. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

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

    2000-01-01

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

  15. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-04-01

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

  16. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-04-01

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

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

    International Nuclear Information System (INIS)

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

    2000-04-01

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

  18. Nuclear Safety Research and Facilities department annual report 1996

    International Nuclear Information System (INIS)

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

    1997-04-01

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

  19. Nuclear Safety Research and Facilities Department annual report 1997

    International Nuclear Information System (INIS)

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

    1998-04-01

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

  20. Self Assessment for the Safety of Research Reactor in Indonesia

    International Nuclear Information System (INIS)

    Melani, Ai; Chang, Soon Heung

    2008-01-01

    At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. National Nuclear Energy Agency (BATAN) has three research reactor; which are: Reactor Triga Mark II at Bandung, Reactor Kartini at Yogyakarta and Reactor Serbaguna (Multi Purpose Reactor) at Serpong. The Code of Conduct on the Safety of Research Reactors establishes 'best practice' guidelines for the licensing, construction and operation of research reactors. In this paper the author use the requirement in code of conduct to review the safety of research reactor in Indonesia