Safety in laboratories: Indian scenario.

Science.gov (United States)

Mustafa, Ajaz; Farooq, A Jan; Qadri, Gj; S A, Tabish

2008-07-01

Health and safety in clinical laboratories is becoming an increasingly important subject as a result of emergence of highly infectious diseases such as Hepatitis and HIV. A cross sectional study was carried out to study the safety measures being adopted in clinical laboratories of India. Heads of laboratories of teaching hospitals of India were subjected to a standardized, pretested questionnaire. Response rate was 44.8%. only 60% of laboratories had person in-charge of safety in laboratory. Seventy three percent of laboratories had safety education program regarding hazards. In 91% of laboratories staff is using protective clothing while working in laboratories. Hazardous material regulations are followed in 78% of laboratories. Regular health check ups are carried among laboratory staff in 43.4% of laboratories.Safety manual is available in 56.5% of laboratories. 73.9% of laboratories are equipped with fire extinguishers. Fume cupboards are provided in 34.7% of laboratories and they are regularly checked in 87.5% of these laboratories. In 78.26% of laboratories suitable measures are taken to minimize formation of aerosols.In 95.6% of laboratories waste is disposed off as per bio-medical waste management handling rules. Laboratory of one private medical college was accredited with NABL and safety parameters were better in that laboratory. Installing safety engineered devices apparently contributes to significant decrease in injuries in laboratories; laboratory safety has to be a part of overall quality assurance programme in hospitals. Accreditation has to be made necessary for all laboratories.

SAFETY IN THE DESIGN OF SCIENCE LABORATORIES AND BUILDING CODES.

Science.gov (United States)

HOROWITZ, HAROLD

THE DESIGN OF COLLEGE AND UNIVERSITY BUILDINGS USED FOR SCIENTIFIC RESEARCH AND EDUCATION IS DISCUSSED IN TERMS OF LABORATORY SAFETY AND BUILDING CODES AND REGULATIONS. MAJOR TOPIC AREAS ARE--(1) SAFETY RELATED DESIGN FEATURES OF SCIENCE LABORATORIES, (2) LABORATORY SAFETY AND BUILDING CODES, AND (3) EVIDENCE OF UNSAFE DESIGN. EXAMPLES EMPHASIZE…

Safety Research Experiment Facilities, Idaho National Engineering Laboratory, Idaho. Draft environmental statement

International Nuclear Information System (INIS)

1977-01-01

This environmental statement was prepared in accordance with the National Environmental Policy Act of 1969 (NEPA) in support of the Energy Research and Development Administration's (ERDA) proposal for legislative authorization and appropriations for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evalution of some design options and in the assessment of the long-term potential risk associated with wide-scale deployment of the FBR

Safety and health: Principles and practices in the laboratory

International Nuclear Information System (INIS)

Fakhrul Razi Ahmadun; Guan, Chuan Teong; Mohd Halim Shah Ismail

2005-01-01

Ignorance, carelessness or improper practices in the laboratory or the improper handling of hazardous or toxic materials may lead to work accidents and work-related ill-health. Laboratory users and administrators cannot afford to overlook these possible consequences due to the misconduct of laboratory practices and should decide how best to manage the health and safety aspects in the laboratory. This book has been written for safety representatives of colleges and universities, for lectures, teachers and students, and for researchers working in laboratories. It is also for everyone responsible for laboratory safety, laboratory accidents and their consequences. The emphasis is on hazards to health and safety, with the focus on the general hazards in the laboratory, how they arise and how to prevent, how to eliminate and control them. Special hazards will also be discussed such as radiation hazards and human factors. This book also provides information on governmental and non-governmental agencies and authorities, emergency contact numbers of relevant authorities, a list of Malaysia occupational safety and health related legislation and some useful occupational safety and health web sites. Readers will find that the information contained in this book will serve as the foundation for laboratory users safety policy. A set of Laboratory Safety Forms for a typical laboratory is also available in the appendix for reference. Laboratory users can use and adapt these forms for their own laboratory requirements. (author)

Safety research experiment facilities, Idaho National Engineering Laboratory, Idaho. Final environmental impact statement

International Nuclear Information System (INIS)

Liverman, J.L.

1977-09-01

This environmental statement was prepared for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evaluation of some design options and in the assessment of the long-term potential risk associated with wide-acale deployment of the FBR

Laboratory Safety Awareness Among General Physics Undergraduate Students

Directory of Open Access Journals (Sweden)

C. O. Ponferrada

2017-12-01

Full Text Available Safety awareness in the laboratory is essential to reduce occupational risks. This study was conducted to determine the students’ safety awareness in a Physics laboratory. This study determined the student perception towards safety awareness by factors of gender and college from which students are enrolled. A sum of 324 students enrolled in Physics10 (Mechanics and Heat and Physics11 (Electricity and Magnetism in the Mindanao University of Science and Technology (MUST were randomly selected as survey respondents. A modified survey questionnaire was used as research instrument. The results show that the students had positive level of safety awareness and perceived positively on the preventive measures to reduce laboratory risk. Further, regardless of gender students enrolled in Physics 10 were more positively aware towards safety awareness than students enrolled in Physics 11. Similarly, a variation among the students perception towards safety awareness from the College of Engineering and Architecture (CEA and College of Industrial and Information Technology (CIIT occurred. Overall, present findings indicate a need to introduce laboratory safety awareness in Physics classes.

Safety analysis report of uranium dioxide fuel laboratory, Nuclear Research Centre Inchas, Egypt

International Nuclear Information System (INIS)

Abdel-Azim, M.S.; Abdel-Halim, A.

1987-07-01

In the Nuclear Research Center Inchas a uranium dioxide fuel laboratory is planned and built by the AEA Cairo (Atomic Energy Authority). The layout of this fuel lab and the programmatical contents are subject to the bilaterial cooperation between Egypt and the Federal Republic of Germany. In this report the safety analysis as basic items for the approval procedure are started in detail. (orig.) [de

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...

Undergraduate Organic Chemistry Laboratory Safety

Science.gov (United States)

Luckenbaugh, Raymond W.

1996-11-01

Each organic chemistry student should become familiar with the educational and governmental laboratory safety requirements. One method for teaching laboratory safety is to assign each student to locate safety resources for a specific class laboratory experiment. The student should obtain toxicity and hazardous information for all chemicals used or produced during the assigned experiment. For example, what is the LD50 or LC50 for each chemical? Are there any specific hazards for these chemicals, carcinogen, mutagen, teratogen, neurotixin, chronic toxin, corrosive, flammable, or explosive agent? The school's "Chemical Hygiene Plan", "Prudent Practices for Handling Hazardous Chemicals in the Laboratory" (National Academy Press), and "Laboratory Standards, Part 1910 - Occupational Safety and Health Standards" (Fed. Register 1/31/90, 55, 3227-3335) should be reviewed for laboratory safety requirements for the assigned experiment. For example, what are the procedures for safe handling of vacuum systems, if a vacuum distillation is used in the assigned experiment? The literature survey must be submitted to the laboratory instructor one week prior to the laboratory session for review and approval. The student should then give a short presentation to the class on the chemicals' toxicity and hazards and describe the safety precautions that must be followed. This procedure gives the student first-hand knowledge on how to find and evaluate information to meet laboartory safety requirements.

Chemistry laboratory safety manual available

Science.gov (United States)

Elsbrock, R. G.

1968-01-01

Chemistry laboratory safety manual outlines safe practices for handling hazardous chemicals and chemistry laboratory equipment. Included are discussions of chemical hazards relating to fire, health, explosion, safety equipment and procedures for certain laboratory techniques and manipulations involving glassware, vacuum equipment, acids, bases, and volatile solvents.

Knowledge and practices of pharmaceutical laboratory workers on laboratory safety

Directory of Open Access Journals (Sweden)

Esra Emerce

2017-09-01

Full Text Available Laboratories are classified as very hazardous workplaces. Objective: The aim of this descriptive study was to determine the knowledge and practice of laboratory safety by analysts and technicians in the laboratories of the Turkish Medicine and Medical Devices Agency. Methods:  85.0% (n=93 of the workers (n=109 was reached. A pre-tested, laboratory safety oriented, self-administered questionnaire was completed under observation. Results: Participants were mostly female (66,7%, had 12.8±8.2 years of laboratory experience and worked 24.6±10.3 hours per week. 53.8% of the employees generally worked with flammable and explosive substances, 29.0% with acute toxic or carcinogenic chemicals and 30.1% with physical dangers. Of all surveyed, 14.0% had never received formal training on laboratory safety. The proportion of ‘always use’ of laboratory coats, gloves, and goggles were 84.9%, 66.7%, and 6.5% respectively. 11.9% of the participants had at least one serious injury throughout their working lives and 24.7% had at least one small injury within the last 6 months. Among these injuries, incisions, bites and tears requiring no stiches (21.0% and the inhalation of chemical vapors (16.1% took first place. The mean value for the number of correct responses to questions on basic safety knowledge was 65.4±26.5, out of a possible 100. Conclusion: Overall, the participants have failed in some safety practices and have been eager to get regular education on laboratory safety.  From this point onwards, it would be appropriate for the employers to organize periodic trainings on laboratory safety.Keywords: Health personnel, laboratory personnel, occupational health, occupational safety, pharmacy

Laboratory safety and the WHO World Alliance for Patient Safety.

Science.gov (United States)

McCay, Layla; Lemer, Claire; Wu, Albert W

2009-06-01

Laboratory medicine has been a pioneer in the field of patient safety; indeed, the College of American Pathology first called attention to the issue in 1946. Delivering reliable laboratory results has long been considered a priority, as the data produced in laboratory medicine have the potential to critically influence individual patients' diagnosis and management. Until recently, most attention on laboratory safety has focused on the analytic stage of laboratory medicine. Addressing this stage has led to significant and impressive improvements in the areas over which laboratories have direct control. However, recent data demonstrate that pre- and post-analytical phases are at least as vulnerable to errors; to further improve patient safety in laboratory medicine, attention must now be focused on the pre- and post-analytic phases, and the concept of patient safety as a multi-disciplinary, multi-stage and multi-system concept better understood. The World Alliance for Patient Safety (WAPS) supports improvement of patient safety globally and provides a potential framework for considering the total testing process.

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

Introducing Laboratory Safety.

Science.gov (United States)

DeLorenzo, Ronald

1985-01-01

Presents a simple, 10-item quiz designed to make students aware that they must learn laboratory safety. The items include questions on acid/base accidents, several types of fire extinguishers, and safety glassses. Answers and some explanations are included. (DH)

[Safety in the Microbiology laboratory].

Science.gov (United States)

Rojo-Molinero, Estrella; Alados, Juan Carlos; de la Pedrosa, Elia Gómez G; Leiva, José; Pérez, José L

2015-01-01

The normal activity in the laboratory of microbiology poses different risks - mainly biological - that can affect the health of their workers, visitors and the community. Routine health examinations (surveillance and prevention), individual awareness of self-protection, hazard identification and risk assessment of laboratory procedures, the adoption of appropriate containment measures, and the use of conscientious microbiological techniques allow laboratory to be a safe place, as records of laboratory-acquired infections and accidents show. Training and information are the cornerstones for designing a comprehensive safety plan for the laboratory. In this article, the basic concepts and the theoretical background on laboratory safety are reviewed, including the main legal regulations. Moreover, practical guidelines are presented for each laboratory to design its own safety plan according its own particular characteristics. Copyright © 2014 Elsevier España, S.L.U. y Sociedad Española de Enfermedades Infecciosas y Microbiología Clínica. All rights reserved.

FOOD SAFETY TESTING LABORATORY

Data.gov (United States)

Federal Laboratory Consortium — This laboratory develops screening assays, tests and modifies biosensor equipment, and optimizes food safety testing protocols for the military and civilian sector...

Laboratory services series: a safety program for service groups in a national research and development laboratory (1965--1974)

International Nuclear Information System (INIS)

Winget, R.H.

1975-11-01

The experiences of a ten-year period of developing a safety program for craft and labor groups supporting a major laboratory are summarized with tabulations of types of injuries or accidents, improvements noted over the decade, and educational and safety recognition efforts

A Laboratory Safety Program at Delaware.

Science.gov (United States)

Whitmyre, George; Sandler, Stanley I.

1986-01-01

Describes a laboratory safety program at the University of Delaware. Includes a history of the program's development, along with standard safety training and inspections now being implemented. Outlines a two-day laboratory safety course given to all graduate students and staff in chemical engineering. (TW)

Status of Safety Precautions in Science Laboratories in Enugu State ...

African Journals Online (AJOL)

This study was conducted to determine the status of safety precautions in science laboratories in Enugu State of Nigeria. Three research questions and two hypotheses guided the study. The research questions include: 1. What are the sources of hazards in school science laboratories? 2. What are the causes of accidents in ...

Methodological proposal for occupational health and safety actions in research laboratories with nanotechnologies activities.

Science.gov (United States)

Andrade, Luís Renato Balbão; Amaral, Fernando Gonçalves

2012-01-01

Nanotechnologies is a multidisciplinary set of techniques to manipulate matter on nanoscale level, more precisely particles below 100 nm whose characteristic due to small size is essentially different from those found in macro form materials. Regarding to these new properties of the materials there are knowledge gaps about the effects of these particles on human organism and the environment. Although it still being considered emerging technology it is growing increasingly fast as well as the number of products using nanotechnologies in some production level and so the number of researchers involved with the subject. Given this scenario and based on literature related, a comprehensive methodology for health and safety at work for researching laboratories with activities in nanotechnologies was developed, based on ILO structure guidelines for safety and health at work system on which a number of nanospecific recommendations were added to. The work intends to offer food for thought on controlling risks associated to nanotechnologies.

OSHA Laboratory Standard: Driving Force for Laboratory Safety!

Science.gov (United States)

Roy, Kenneth R.

2000-01-01

Discusses the Occupational Safety and Health Administration's (OSHA's) Laboratory Safety Standards as the major driving force in establishing and maintaining a safe working environment for teachers and students. (Author)

Handbook of laboratory health and safety measures

International Nuclear Information System (INIS)

Pal, S.B.

1985-01-01

The application of radioactive isotopes and various scientific instruments based on different ionizing and non-ionizing radiation have brought new safety problems to laboratory workers today. Therefore, there is a need to revise present knowledge of safety measures to deal with new hazards, thus broadening the outlook towards health and safety measures for contemporary laboratory staff. This handbook presents a series of articles on current knowledge regarding laboratory safety

Radiation safety requirements for radionuclide laboratories

International Nuclear Information System (INIS)

1993-01-01

In accordance with the section 26 of the Finnish Radiation Act (592/91) the safety requirements to be taken into account in planning laboratories and other premises, which affect safety in the use of radioactive materials, are confirmed by the Finnish Centre for Radiation and Nuclear Safety. The guide specifies the requirements for laboratories and storage rooms in which radioactive materials are used or stored as unsealed sources. There are also some general instructions concerning work procedures in a radionuclide laboratory

Safety management and risk assessment in chemical laboratories.

Science.gov (United States)

Marendaz, Jean-Luc; Friedrich, Kirstin; Meyer, Thierry

2011-01-01

The present paper highlights a new safety management program, MICE (Management, Information, Control and Emergency), which has been specifically adapted for the academic environment. The process starts with an exhaustive hazard inventory supported by a platform assembling specific hazards encountered in laboratories and their subsequent classification. A proof of concept is given by a series of implementations in the domain of chemistry targeting workplace health protection. The methodology is expressed through three examples to illustrate how the MICE program can be used to address safety concerns regarding chemicals, strong magnetic fields and nanoparticles in research laboratories. A comprehensive chemical management program is also depicted.

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.

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

Laboratory Safety Guide for Arkansas K-12 Schools.

Science.gov (United States)

Arkansas State Dept. of Education, Little Rock.

This document presents laboratory safety rules for Arkansas K-12 schools which were developed by the Arkansas Science Teachers Association (ASTA) and the Arkansas Department of Education (ADE). Contents include: (1) "Laboratory Safety Guide for Arkansas K-12 Schools"; (2) "Safety Considerations"; (3) "Safety Standards for Science Laboratories";…

Research program on nuclear technology and nuclear safety

International Nuclear Information System (INIS)

Dreier, J.

2010-04-01

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 nuclear technology and nuclear safety. Work carried out, knowledge gained and results obtained in the various areas are reported on. These include projects carried out in the Laboratory for Reactor Physics and System Behaviour LRS, the LTH Thermohydraulics Laboratory, the Laboratory for Nuclear Materials LNM, the Laboratory for Final Storage Safety LES and the Laboratory for Energy Systems Analysis LEA of the Paul Scherrer Institute PSI. Work done in 2009 and results obtained are reported on, including research on transients in Swiss reactors, risk and human reliability. Work on the 'Proteus' research reactor is reported on, as is work done on component safety. International co-operation in the area of serious accidents and the disposal of nuclear wastes is reported on. Future concepts for reactors and plant life management are discussed. The energy business in general is also discussed. Finally, national and international co-operation is noted and work to be done in 2010 is reviewed

Safety in the Chemical Laboratory: An Undergraduate Chemical Laboratory Safety Course.

Science.gov (United States)

Nicholls, L. Jewel

1982-01-01

Describes a two-quarter hour college chemistry course focusing on laboratory safety. Includes lists of topics/assignments, problem sets (toxicology, storage, and energy) and videotapes, films, and slide sets used in the course. (JN)

School Chemistry Laboratory Safety Guide

Science.gov (United States)

Brundage, Patricia; Palassis, John

2006-01-01

The guide presents information about ordering, using, storing, and maintaining chemicals in the high school laboratory. The guide also provides information about chemical waste, safety and emergency equipment, assessing chemical hazards, common safety symbols and signs, and fundamental resources relating to chemical safety, such as Material…

Integration of Behaviour-Based Safety Programme into Engineering Laboratories and Workshops Conceptually

Science.gov (United States)

Koo, Kean Eng; Zain, Ahmad Nurulazam Md; Zainal, Siti Rohaida Mohamed

2012-01-01

The purpose of this conceptual research framework is to develop and integrate a safety training model using a behaviour-based safety training programme into laboratories for young adults, during their tertiary education, particularly in technical and vocational education. Hence, this research will be investigating the outcome of basic safety…

High-pressure safety at the Lawrence Livermore Laboratory, an energy research facility

International Nuclear Information System (INIS)

Burton, W.A.

1976-01-01

The high-pressure safety program at Lawrence Livermore Laboratory, Livermore, California, has been successful in preventing lost-time high-pressure accidents over the past 12 years. Program organization, personnel training and qualification, pressure vessel design criteria and documentation, and pressure testing and inspection are discussed

Biomonitoring at the UK Health and Safety Laboratory.

Science.gov (United States)

Cocker, J; Jones, K; Morton, J; Mason, H J

2007-05-01

The UK Health and Safety Laboratory (HSL) provides research and analytical support to the Health and Safety Executive, other Government Departments and employers. In the area of biomonitoring HSL conducts research studies and provides an analytical service for regular surveillance of worker exposure to hazardous substances. This paper gives brief examples of how data from such studies can be used to develop biological monitoring guidance values for isocyanates, polycyclic aromatic hydrocarbons and hexavalent chromium. In addition, a study of occupational exposure to copper chrome arsenic wood preservatives is briefly described to show how biological monitoring can be used for post-approval surveillance of a biocide.

Research and Progress on Virtual Cloud Laboratory

Directory of Open Access Journals (Sweden)

Zhang Jian Wei

2016-01-01

Full Text Available In recent years, cloud computing technology has experienced continuous development and improvement, and has gradually expanded to the education sector. First, this paper will introduce the background knowledge of the current virtual cloud laboratory; by comparing the advantages and disadvantages between traditional laboratory and virtual cloud laboratory, and comparing the application, advantages and disadvantages, and development trend of OpenStack technology and VMWare technology in safety, performance, design, function, use case, and value of virtual cloud laboratory, this paper concludes that application based on OpenStack virtual cloud laboratory in universities and research institutes and other departments is essential.

Safety management procedures and practices at Indira Gandhi Centre for Atomic Research

Energy Technology Data Exchange (ETDEWEB)

Rodriguez, P.; Lee, S.M.; Kapoor, R.P.; Raghunath, V.M.; Karthikeyan, S.V. [Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India)]. E-mail: kapoor@igcar.ernet.in

2004-07-01

The Indira Gandhi Centre for Atomic Research (IGCAR) operates FBTR (Fast Breeder Test Reactor), KAMINI (neutron source reactor), radiometallurgical laboratory, radiochemical laboratory, reprocessing plant, industrial scale sodium loops, advanced research laboratories, workshops, etc. Codified safety management procedures with systematic surveillance are essential for safe and reliable operations and these are described under the classifications of radiation safety, industrial safety and reactor operations with special emphasis on the human factor. Health physics teams, independent of the plant facility, supervise the radioactive facilities of the centre. Industrial safety standards are maintained by another independent section. Safety management for the reactors include a clear organisational structure, adequate documentation, compulsory training and licencing, safe working methods taking into account human factors and review by independent safety authorities. (author)

Safety management procedures and practices at Indira Gandhi Centre for Atomic Research

International Nuclear Information System (INIS)

Rodriguez, P.; Lee, S.M.; Kapoor, R.P.; Raghunath, V.M.; Karthikeyan, S.V.

2004-01-01

The Indira Gandhi Centre for Atomic Research (IGCAR) operates FBTR (Fast Breeder Test Reactor), KAMINI (neutron source reactor), radiometallurgical laboratory, radiochemical laboratory, reprocessing plant, industrial scale sodium loops, advanced research laboratories, workshops, etc. Codified safety management procedures with systematic surveillance are essential for safe and reliable operations and these are described under the classifications of radiation safety, industrial safety and reactor operations with special emphasis on the human factor. Health physics teams, independent of the plant facility, supervise the radioactive facilities of the centre. Industrial safety standards are maintained by another independent section. Safety management for the reactors include a clear organisational structure, adequate documentation, compulsory training and licencing, safe working methods taking into account human factors and review by independent safety authorities. (author)

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

GaInSn usage in the research laboratory

International Nuclear Information System (INIS)

Morley, N. B.; Burris, J.; Cadwallader, L. C.; Nornberg, M. D.

2008-01-01

GaInSn, a eutectic alloy, has been successfully used in the Magneto-Thermofluid Research Laboratory at the University of California-Los Angeles and at the Princeton Plasma Physics Laboratory for the past six years. This paper describes the handling and safety of GaInSn based on the experience gained in these institutions, augmented by observations from other researchers in the liquid metal experimental community. GaInSn is an alloy with benign properties and shows considerable potential in liquid metal experimental research and cooling applications

Health and safety in clinical laboratories in developing countries: safety considerations.

Science.gov (United States)

Ejilemele, A A; Ojule, A C

2004-01-01

Clinical laboratories are potentially hazardous work areas. Health and safety in clinical laboratories is becoming an increasingly important subject as a result of the emergence of highly infectious diseases such as hepatitis and HIV. This is even more so in developing countries where health and safety have traditionally been regarded as low priority issues, considering the more important health problems confronting the health authorities in these countries. We conducted a literature search using the medical subheadings titles on the INTERNET over a period of twenty years and summarized our findings. This article identifies hazards in the laboratories and highlights measures to make the laboratory a safer work place. It also emphasizes the mandatory obligations of employers and employees towards the attainment of acceptable safety standards in clinical laboratories in Third World countries in the face of the current HIV/AIDS epidemic in many of these developing countries especially in the sub-Saharan Africa while accommodating the increasing work load in these laboratories. Both the employer and the employee have major roles to play in the maintenance of a safe working environment. This can be achieved if measures discussed are incorporated into everyday laboratory practice.

Safety Teams: An Approach to Engage Students in Laboratory Safety

Science.gov (United States)

Alaimo, Peter J.; Langenhan, Joseph M.; Tanner, Martha J.; Ferrenberg, Scott M.

2010-01-01

We developed and implemented a yearlong safety program into our organic chemistry lab courses that aims to enhance student attitudes toward safety and to ensure students learn to recognize, demonstrate, and assess safe laboratory practices. This active, collaborative program involves the use of student "safety teams" and includes…

An Analysis of Laboratory Safety in Texas.

Science.gov (United States)

Fuller, Edward J.; Picucci, Ali Callicoatte; Collins, James W.; Swann, Philip

This paper reports on a survey to discover the types of laboratory accidents that occur in Texas public schools, the factors associated with such accidents, and the practices of schools with regard to current laboratory safety requirements. The purpose of the survey is to better understand safety conditions in Texas public schools and to help…

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

LABORATORY DESIGN CONSIDERATIONS FOR SAFETY.

Science.gov (United States)

National Safety Council, Chicago, IL. Campus Safety Association.

THIS SET OF CONSIDERATIONS HAS BEEN PREPARED TO PROVIDE PERSONS WORKING ON THE DESIGN OF NEW OR REMODELED LABORATORY FACILITIES WITH A SUITABLE REFERENCE GUIDE TO DESIGN SAFETY. THERE IS NO DISTINCTION BETWEEN TYPES OF LABORATORY AND THE EMPHASIS IS ON GIVING GUIDES AND ALTERNATIVES RATHER THAN DETAILED SPECIFICATIONS. AREAS COVERED INCLUDE--(1)…

Radiation protection in a multi-disciplinary research laboratory

International Nuclear Information System (INIS)

O'Donovan, E.J.B.; Jenks, G.J.; Brighton, D.R.

1993-01-01

This paper describes the measures for the protection of personnel against the hazards of ionising and non-ionising radiation at the Materials Research Laboratory (MRL) in Victoria. The paper describes MRL safety and protection policy and management, and gives brief details of procedures and problems at the working level. A comparison of MRL average annual photon doses with all Governmental Research Institutions and industry is given. The good safety record of MRL is evident and shows that the radioactive protection issues are well handled. 4 figs

An Innovative Multimedia Approach to Laboratory Safety

Science.gov (United States)

Anderson, M. B.; Constant, K. P.

1996-01-01

A new approach for teaching safe laboratory practices has been developed for materials science laboratories at Iowa State university. Students are required to complete a computerized safety tutorial and pass an exam before working in the laboratory. The safety tutorial includes sections on chemical, electrical, radiation, and high temperature safety. The tutorial makes use of a variety of interactions, including 'assembly' interactions where a student is asked to drag and drop items with the mouse (either labels or pictures) to an appropriate place on the screen (sometimes in a specific order). This is extremely useful for demonstrating safe lab practices and disaster scenarios. Built into the software is a record tracking scheme so that a professor can access a file that records which students have completed the tutorial and their scores on the exam. This paper will describe the development and assessment of the safety tutorials.

Health, Safety and Environmental Risk Assessment in Laboratory Sites

Directory of Open Access Journals (Sweden)

2012-05-01

Full Text Available Introduction: ”Exposing to danger” or in other words, “risk” is a process which is led to an uncertain result in every field. Project risks are uncertain contingent events or situations that if they occur will have positive or negative effects on project’s objectives. Todays, research and educational process and more complicated and the professional risk management become much more difficult, as a result. .Material and Method: In this research, the health and safety issues have been studied and analyzed using ISO 14121 and the environmental issues by EMEA to determine the risk level separately for research laboratories and to prioritize corrective measure in each field (school. .Result: The finding in this study showed that from all the main risks within the rage of 38-86 percent have been decreased. Moreover average of the risk level for the health, safety and environment cases showed a significant decrease (Pvalue<0.0001 by implement controlling and protective countermeasures compariy to the priority state without any measures. . Conclusion: The risk assessment with hazards control strategy based on ISO 14121 is a compatible method in laboratory site as universities and other reasearch sites.

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

Laboratory Directed Research and Development FY 2000

International Nuclear Information System (INIS)

Hansen, Todd; Levy, Karin

2001-01-01

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Annual report on Laboratory Directed Research and Development for FY2000

The Influence of Laboratory Safety on Capital Planning.

Science.gov (United States)

Francis, Robert A.

1980-01-01

Discusses state and federal legislation concerning the handling of dangerous materials and its impact on the design of college and university buildings. Lists federal legislation affecting laboratory safety, the objectives of each act, and the influence of each act on laboratory safety. (IRT)

Technical Safety Appraisal of the Lawrence Livermore National Laboratory

Energy Technology Data Exchange (ETDEWEB)

1990-12-01

This report documents the results of the Technical Safety Appraisal (TSA) of the Lawrence Livermore National Laboratory (LLNL) (including the Site 300 area), Livermore, California, conducted from February 26 to April 5, 1990. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety and Health (ES H) Programs at LLNL. LLNL is operated by the University of California for the Department of Energy (DOE), and is a multi-program, mission-oriented institution engaged in fundamental and applied research programs that require a multidisciplinary approach. 1 fig.

Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

International Nuclear Information System (INIS)

Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

2009-01-01

In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

Laboratory research irradiators with enhanced security features

International Nuclear Information System (INIS)

Srivastava, Piyush

2016-01-01

Over the years BRIT has developed state of art technology for laboratory research irradiators which are suited most for carrying out research and development works in the fields of radiation processing. These equipment which house radioactive sources up to 14 kCi are having a number of features to meet users requirements. They are manufactured as per the national and International standards of safety codes. The paper deals with design, development and application aspects of laboratory research irradiator called Gamma Chamber and also the new security features planned for incorporation in the equipment. Equipment are being regularly manufactured, supplied and installed by BRIT in India and Abroad. There is a number of such equipment in use at different institutions and are found to be very useful. (author)

Laboratory research irradiators with enhanced security features

International Nuclear Information System (INIS)

Srivastava, Piyush

2014-01-01

Over the years BRIT has developed state of art technology for laboratory research irradiators which are suited most for carrying out research and development works in the fields of radiation processing. These equipment which house radioactive sources up to 14 kCi are having a number of features to meet users requirements. They are manufactured as per the national and International standards of safety codes. The paper deals with design, development and application aspects of laboratory research irradiator called Gamma Chamber and also the new security features planned for incorporation in the equipment. Equipment are being regularly manufactured, supplied and installed by BRIT in India and Abroad. There are a number of such equipment in use at different institutions and are found to be very useful. (author)

Tritium Research Laboratory safety analysis report

Energy Technology Data Exchange (ETDEWEB)

Wright, D.A.

1979-03-01

Design and operational philosophy has been evolved to keep radiation exposures to personnel and radiation releases to the environment as low as reasonably achievable. Each experiment will be doubly contained in a glove box and will be limited to 10 grams of tritium gas. Specially designed solid-hydride storage beds may be used to store temporarily up to 25 grams of tritium in the form of tritides. To evaluate possible risks to the public or the environment, a review of the Sandia Laboratories Livermore (SLL) site was carried out. Considered were location, population, land use, meteorology, hydrology, geology, and seismology. The risks and the extent of damage to the TRL and vital systems were evaluated for flooding, lightning, severe winds, earthquakes, explosions, and fires. All of the natural phenomena and human error accidents were considered credible, although the extent of potential damage varied. However, rather than address the myriad of specific individual consequences of each accident scenario, a worst-case tritium release caused indirectly by an unspecified natural phenomenon or human error was evaluated. The maximum credible radiological accident is postulated to result from the release of the maximum quantity of gas from one experiment. Thus 10 grams of tritium gas was used in the analysis to conservatively estimate the maximum whole-body dose of 1 rem at the site boundary and a maximum population dose of 600 man-rem. Accidental release of this amount of tritium implies simultaneous failure of two doubly contained systems, an occurrence considered not credible. Nuclear criticality is impossible in this facility. Based upon the analyses performed for this report, we conclude that the Tritium Research Laboratory can be operated without undue risk to employees, the general public, or the environment. (ERB)

Tritium Research Laboratory safety analysis report

International Nuclear Information System (INIS)

Wright, D.A.

1979-03-01

Design and operational philosophy has been evolved to keep radiation exposures to personnel and radiation releases to the environment as low as reasonably achievable. Each experiment will be doubly contained in a glove box and will be limited to 10 grams of tritium gas. Specially designed solid-hydride storage beds may be used to store temporarily up to 25 grams of tritium in the form of tritides. To evaluate possible risks to the public or the environment, a review of the Sandia Laboratories Livermore (SLL) site was carried out. Considered were location, population, land use, meteorology, hydrology, geology, and seismology. The risks and the extent of damage to the TRL and vital systems were evaluated for flooding, lightning, severe winds, earthquakes, explosions, and fires. All of the natural phenomena and human error accidents were considered credible, although the extent of potential damage varied. However, rather than address the myriad of specific individual consequences of each accident scenario, a worst-case tritium release caused indirectly by an unspecified natural phenomenon or human error was evaluated. The maximum credible radiological accident is postulated to result from the release of the maximum quantity of gas from one experiment. Thus 10 grams of tritium gas was used in the analysis to conservatively estimate the maximum whole-body dose of 1 rem at the site boundary and a maximum population dose of 600 man-rem. Accidental release of this amount of tritium implies simultaneous failure of two doubly contained systems, an occurrence considered not credible. Nuclear criticality is impossible in this facility. Based upon the analyses performed for this report, we conclude that the Tritium Research Laboratory can be operated without undue risk to employees, the general public, or the environment

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

International Nuclear Information System (INIS)

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

1987-02-01

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

The Microscale Inorganic Laboratory: Safety, Economy and Versatility.

Science.gov (United States)

Szafran, Zvi; And Others

1989-01-01

Discussed are four major advantages to the use of microscale laboratories for teaching chemistry. Included are effects on waste generation, laboratory safety, reagent variety, and laboratory efficiency. (CW)

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

Safety and health practice among laboratory staff in Malaysian education sector

Science.gov (United States)

Husna Che Hassan, Nurul; Rasdan Ismail, Ahmad; Kamilah Makhtar, Nor; Azwadi Sulaiman, Muhammad; Syuhadah Subki, Noor; Adilah Hamzah, Noor

2017-10-01

Safety is the most important issue in industrial sector such as construction and manufacturing. Recently, the increasing number of accident cases reported involving school environment shows the important of safety issues in education sector. Safety awareness among staff in this sector is crucial in order to find out the method to prevent the accident occurred in future. This study was conducted to analyze the knowledge of laboratory staff in term of safety and health practice in laboratory. Survey questionnaires were distributing among 255 of staff laboratory from ten District Education Offices in Kelantan. Descriptive analysis shows that the understanding of safety and health practice are low while doing some job activities in laboratory. Furthermore, some of the staff also did not implemented safety practice that may contribute to unplanned event occur in laboratory. Suggestion that the staff at laboratory need to undergo on Occupational Safety and Health training to maintain and create safe environment in workplaces.

Laboratory errors and patient safety.

Science.gov (United States)

Miligy, Dawlat A

2015-01-01

Laboratory data are extensively used in medical practice; consequently, laboratory errors have a tremendous impact on patient safety. Therefore, programs designed to identify and reduce laboratory errors, as well as, setting specific strategies are required to minimize these errors and improve patient safety. The purpose of this paper is to identify part of the commonly encountered laboratory errors throughout our practice in laboratory work, their hazards on patient health care and some measures and recommendations to minimize or to eliminate these errors. Recording the encountered laboratory errors during May 2008 and their statistical evaluation (using simple percent distribution) have been done in the department of laboratory of one of the private hospitals in Egypt. Errors have been classified according to the laboratory phases and according to their implication on patient health. Data obtained out of 1,600 testing procedure revealed that the total number of encountered errors is 14 tests (0.87 percent of total testing procedures). Most of the encountered errors lay in the pre- and post-analytic phases of testing cycle (representing 35.7 and 50 percent, respectively, of total errors). While the number of test errors encountered in the analytic phase represented only 14.3 percent of total errors. About 85.7 percent of total errors were of non-significant implication on patients health being detected before test reports have been submitted to the patients. On the other hand, the number of test errors that have been already submitted to patients and reach the physician represented 14.3 percent of total errors. Only 7.1 percent of the errors could have an impact on patient diagnosis. The findings of this study were concomitant with those published from the USA and other countries. This proves that laboratory problems are universal and need general standardization and bench marking measures. Original being the first data published from Arabic countries that

Inquiry relating to safety due to modification of usage of nuclear fuel material (establishment of waste safety testing facility) in Tokai Laboratory, Japan Atomic Energy Research Institute

International Nuclear Information System (INIS)

1979-01-01

Application was made to the director of the Science and Technology Agency (STA) for the license relating to the modification of usage of nuclear fuel material (the establishment of waste safety testing facility) from the director of the Japan Atomic Energy Research Institute on November 30, 1978. After passing through the safety evaluation in the Nuclear Safety Bureau of STA, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 6, 1979, from the director of the STA. The head of AESC directed to conduct the safety examination to the head of the Nuclear Fuel Safety Examination Specialist Committee on June 7, 1979. The content of the modification of usage of nuclear fuel material is the establishment of waste safety testing facility to study and test the safety relating to the treatment and disposal of high level radioactive liquid wastes due to the reprocessing of spent fuel. As for the results of the safety examination, the siting of the waste safety testing facility which is located in the Tokai Laboratory, Japan Atomic Energy Research Institute (JAERI), and the test plan of the glass solidification of high level radioactive liquid are presented as the outline of the study plan. The building, main equipments including six cells, the isolation room and the glove box, the storage, and the disposal facilities for gas, liquid and solid wastes are explained as the outline of the facilities. Concerning the items from the viewpoint of safety, aseismatic design, slightly vacuum operation, shielding, decay heat removal, fire protection, explosion protection, criticality management, radiation management and environmental effect were evaluated, and the safety was confirmed. (Nakai, Y.)

Laboratory Directed Research and Development FY 2000

Energy Technology Data Exchange (ETDEWEB)

Hansen, Todd; Levy, Karin

2001-02-27

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Annual report on Laboratory Directed Research and Development for FY2000.

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)

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)

Nuclear Safety Research and Facilities Department annual report 1998

International Nuclear Information System (INIS)

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

1999-04-01

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

Idaho National Laboratory - Nuclear Research Center

International Nuclear Information System (INIS)

Zaidi, M.K.

2005-01-01

Full text: The Idaho National Laboratory is committed to the providing international nuclear leadership for the 21st Century, developing and demonstrating compiling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multiprogram national laboratories. INL runs three major programs - Nuclear, Security and Science. nuclear programs covers the Advanced test reactor, Six Generation technology concepts selected for R and D, Targeting tumors - Boron Neutron capture therapy. Homeland security - Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science - INL facility established for Geocentrifuge Research, Idaho Laboratory, a Utah company achieved major milestone in hydrogen research and INL uses extremophile bacteria to ease bleaching's environmental cost. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (Inset). The institute will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer Inset is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'

Role of a quality management system in improving patient safety - laboratory aspects.

Science.gov (United States)

Allen, Lynn C

2013-09-01

The aim of this study is to describe how implementation of a quality management system (QMS) based on ISO 15189 enhances patient safety. A literature review showed that several European hospitals implemented a QMS based on ISO 9001 and assessed the impact on patient safety. An Internet search showed that problems affecting patient safety have occurred in a number of laboratories across Canada. The requirements of a QMS based on ISO 15189 are outlined, and the impact of the implementation of each requirement on patient safety is summarized. The Quality Management Program - Laboratory Services in Ontario is briefly described, and the experience of Ontario laboratories with Ontario Laboratory Accreditation, based on ISO 15189, is outlined. Several hospitals that implemented ISO 9001 reported either a positive impact or no impact on patient safety. Patient safety problems in Canadian laboratories are described. Implementation of each requirement of the QMS can be seen to have a positive effect on patient safety. Average laboratory conformance on Ontario Laboratory Accreditation is very high, and laboratories must address and resolve any nonconformities. Other standards, practices, and quality requirements may also contribute to patient safety. Implementation of a QMS based on ISO 15189 provides a solid foundation for quality in the laboratory and enhances patient safety. It helps to prevent patient safety issues; when such issues do occur, effective processes are in place for investigation and resolution. Patient safety problems in Canadian laboratories might have been prevented had effective QMSs been in place. Ontario Laboratory Accreditation has had a positive impact on quality in Ontario laboratories. Copyright © 2013 The Canadian Society of Clinical Chemists. Published by Elsevier Inc. All rights reserved.

A Tool for Assessment of Animal Health Laboratory Safety and Biosecurity: The Safety Module of the Food and Agriculture Organization’s Laboratory Mapping Tool

Directory of Open Access Journals (Sweden)

Beatrice Mouillé

2018-03-01

Full Text Available The Laboratory Management Tool (LMT is a standardized spreadsheet-based assessment tool developed to help support national, regional, and global efforts to maintain an effective network of animal health and veterinary public health laboratories. The safety and biosecurity module of the LMT (LMT-S includes 98 measures covering administrative, operational, engineering, and personal protective equipment practices used to provide laboratory safety and biosecurity. Performance aspects of laboratory infrastructure and technical compliance considered fundamental for ensuring that a laboratory is able to appropriately function in a safe and biosecure manner are systematically queried and scored for compliance on a four-point scale providing for a semi-quantitative assessment. Data collected is used to generate graphs and tables mapping levels of compliance with international standards and good practices, as well as for documenting progress over time. The LMT-S was employed by trained auditors in 34 laboratories located in 19 countries between 2015 and 2017. The tool is intended to help standardize animal health laboratory assessments, document compliance with recognized laboratory safety and biosecurity measures, serve as a self-help and training tool, and assist global laboratory development efforts by providing an accurate measurement of laboratory safety and biosecurity at local, national, and regional levels.

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)

The status of safety in the public high school chemistry laboratories in Mississippi

Science.gov (United States)

Lacy, Sarah Louise Trotman

Since laboratory-based science courses have become an essential element of any science curriculum and are required by the Mississippi Department of Education for graduation, the chemistry laboratories in the public high schools in Mississippi must be safe. The purpose of this study was to determine: the safety characteristics of a high school chemistry laboratory; the perceived safety characteristics of the chemistry laboratories in public high schools in Mississippi; the basic safety knowledge of chemistry teachers in public high schools in Mississippi, where chemistry teachers in Mississippi gain knowledge about laboratory safety and instruction; if public high school chemistry laboratories in Mississippi adhere to recommended class size, laboratory floor space per student, safety education, safety equipment, and chemical storage; and the relationship between teacher knowledge of chemistry laboratory safety and the safety status of the laboratory in which they teach. The survey instrument was composed of three parts. Part I Teacher Knowledge consisted of 23 questions concerning high school chemistry laboratory safety. Part II Chemistry Laboratory Safety Information consisted of 40 items divided into four areas of interest concerning safety in high school chemistry laboratories. Part III Demographics consisted of 11 questions relating to teacher certification, experience, education, and safety training. The survey was mailed to a designated chemistry teacher in every public high school in Mississippi. The responses to Part I of the survey indicated that the majority of the teachers have a good understanding of knowledge about chemistry laboratory safety but need more instruction on the requirements for a safe high school chemistry laboratory. Less than 50% of the responding teachers thought they had received adequate preparation from their college classes to conduct a safe chemistry laboratory. According to the responses of the teachers, most of their high school

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)

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....

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.

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)

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

The French underground research laboratory program, contribution to the feasibility and safety studies of geological disposal

International Nuclear Information System (INIS)

Hoorelbeke, J.M.; Niezborala, J.M.; Ben Slimane, K.

2001-01-01

The paper presents the content of the research program to be performed during the construction and the operation of the National Agency for Radioactive Waste Management's (ANDRA) underground laboratory, located in the east of France. The general architecture of the program is presented. Emphasis is put on an iterative process, the purpose of which is mainly to: Prepare site behavior models before starting each phase of the field work (bore hole drilling, shaft sinking, construction of underground galleries, specific experiments); Test and check each model through actual observations and measurements; Adjust the models to take into account the results of the former phase and predict the results expected during the following one. All these models, after validation, will be exploited during the assessment of the safety related performance of the components of the potential repository as well as the whole facility; Obtain necessary data related to the feasibility study of the disposal facility (mechanical design, thermal design, etc.,) and its safety assessment. The relationship between the experimental program, the conceptual design program and the safety evaluation program is explained in order to reach the project objectives which is the final document set to be provided to French authorities in 2006 according to the French law of December 1991. (author)

Radiation safety. Handbook for laboratory workers in the USA

International Nuclear Information System (INIS)

Hotte, E.D.; Krueger, D.J.; Connor, K.

2000-01-01

The aim of the Handbook is to provide a source of information on radiation safety for those who are involved in the use of ionizing radiation in the laboratory. The potential reader may be a laboratory worker in the university or biomedical setting or the safety professional who desires a basic understanding of radiation protection within the research environment. The Handbook may be used as a reference by the radiation protection specialist or Radiation Safety Officer. To this end, liberal use is made of Appendices to make the Handbook a source of reference for a wide spectrum of readership while avoiding complicating the main body of the text. Each chapter or appendix is designed to stand alone. A complete reading of the Handbook will show that topics may be covered more than once. For example, one may read about the hazards and protective measures on handling radioiodine in Chapter 5 on Practical Radiation Protection as well as in Appendix 19 on Safe Handling of 125 I. Extensive use of figures, rather than tables has been made to present data, in the belief that these produce a good visual representation to a level of precision which is sufficient for most purposes of radiation protection in laboratories. The reader must remember that this Handbook should be taken as a guide only to the applicable regulations. You must consult the appropriate state or federal regulation directly or receive advice of a qualified radiation safety professional. Also, some information in the Appendices, such as commercially available training institutions or radioactive waste brokers, may change with time. Telephone numbers are given for the reader to call directly and check the services provided

Laboratory directed research development annual report. Fiscal year 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

This document comprises Pacific Northwest National Laboratory`s report for Fiscal Year 1996 on research and development programs. The document contains 161 project summaries in 16 areas of research and development. The 16 areas of research and development reported on are: atmospheric sciences, biotechnology, chemical instrumentation and analysis, computer and information science, ecological science, electronics and sensors, health protection and dosimetry, hydrological and geologic sciences, marine sciences, materials science and engineering, molecular science, process science and engineering, risk and safety analysis, socio-technical systems analysis, statistics and applied mathematics, and thermal and energy systems. In addition, this report provides an overview of the research and development program, program management, program funding, and Fiscal Year 1997 projects.

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

Accelerator safety program at the Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

Graham, C.L.

1976-01-01

A proposed accelerator safety standard for the Lawrence Livermore Laboratory (LLL) is given. All accelerators will comply with this standard when it is included in the LLL Health and Safety Manual. The radiation alarm and radiation safety system for a radiography facility are also described

Laboratory Directed Research and Development Program. FY 1993

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

This report is compiled from annual reports submitted by principal investigators following the close of fiscal year 1993. This report describes the projects supported and summarizes their accomplishments. The program advances the Laboratory`s core competencies, foundations, scientific capability, and permits exploration of exciting new opportunities. Reports are given from the following divisions: Accelerator and Fusion Research, Chemical Sciences, Earth Sciences, Energy and Environment, Engineering, Environment -- Health and Safety, Information and Computing Sciences, Life Sciences, Materials Sciences, Nuclear Science, Physics, and Structural Biology. (GHH)

Review of radiation safety in the cardiac catheterization laboratory

International Nuclear Information System (INIS)

Johnson, L.W.; Moore, R.J.; Balter, S.

1992-01-01

With the increasing use of coronary arteriography and interventional procedures, radiation exposure to patients and personnel working in cardiac catheterization laboratories has increased. Proper technique to minimize both patient and operator exposure is necessary. A practical approach to radiation safety in the cardiac catheterization laboratory is presented. This discussion should be useful to facilities with well-established radiation safety programs as well as facilities that require restructuring to cope with the radiation environment in a modern cardiac catheterization laboratory

Bulletin of the Research Laboratory for Nuclear Reactors

International Nuclear Information System (INIS)

Aritomi, Masanori

2008-01-01

The bulletin consists of two parts. The first part includes General Research Report. The Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology has three engineering divisions such as Energy Engineering, Mass Transmutation Engineering, and System and Safety Engineering. In this part, 17 reports of Energy Engineering division, 8 reports of Mass transmutation Engineering division, 11 reports of System and Safety Engineering division are described as their activities. In addition, 3 reports of Cooperative Researches are also summarized. The second part is Special Issue about COE-INES RESEARCH REPORT 2007. In this part, 3 reports of Innovative Reactor Group, 2 reports of Innovative Nuclear Energy Utilization System Group, 3 reports of Innovative Transmutation/Separation Group, 2 reports of Relationship between Nuclear and Society Group, 1 report of RA Students in the COE-INES Captainship Educational Program are described as results to their researches. (J.P.N.)

Environment Health & Safety Research Program. Organization and 1979-1980 Publications

Energy Technology Data Exchange (ETDEWEB)

None

1981-01-01

This document was prepared to assist readers in understanding the organization of Pacific Northwest Laboratory, and the organization and functions of the Environment, Health and Safety Research Program Office. Telephone numbers of the principal management staff are provided. Also included is a list of 1979 and 1980 publications reporting on work performed in the Environment, Health and Safety Research Program, as well as a list of papers submitted for publication.

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)

A tool for assessment of animal health laboratory safety and biosecurity: The safety module of the Food and Agriculture Organization’s laboratory mapping tool

OpenAIRE

Mouillé, B; Dauphin, G; Wiersma, L; Blacksell, SD; Claes, F; Kalpravidh, W; Kabore, Y; Hietala, S

2018-01-01

The Laboratory Management Tool (LMT) is a standardized spreadsheet-based assessment tool developed to help support national, regional, and global efforts to maintain an effective network of animal health and veterinary public health laboratories. The safety and biosecurity module of the LMT (LMT-S) includes 98 measures covering administrative, operational, engineering, and personal protective equipment practices used to provide laboratory safety and biosecurity. Performance aspects of laborat...

Laboratory directed research and development program FY 1999

Energy Technology Data Exchange (ETDEWEB)

Hansen, Todd; Levy, Karin

2000-03-08

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. This is the annual report on Laboratory Directed Research and Development (LDRD) program for FY99.

Laboratory Directed Research and Development Program FY 2001

Energy Technology Data Exchange (ETDEWEB)

Hansen, Todd; Levy, Karin

2002-03-15

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. This is the annual report on Laboratory Directed Research and Development (LDRD) program for FY01.

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

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

Survey of safety practices among hospital laboratories in Oromia Regional State, Ethiopia.

Science.gov (United States)

Sewunet, Tsegaye; Kebede, Wakjira; Wondafrash, Beyene; Workalemau, Bereket; Abebe, Gemeda

2014-10-01

Unsafe working practices, working environments, disposable waste products, and chemicals in clinical laboratories contribute to infectious and non-infectious hazards. Staffs, the community, and patients are less safe. Furthermore, such practices compromise the quality of laboratory services. We conducted a study to describe safety practices in public hospital laboratories of Oromia Regional State, Ethiopia. Randomly selected ten public hospital laboratories in Oromia Regional State were studied from Oct 2011- Feb 2012. Self-administered structured questionnaire and observation checklists were used for data collection. The respondents were heads of the laboratories, senior technicians, and safety officers. The questionnaire addressed biosafety label, microbial hazards, chemical hazards, physical/mechanical hazards, personal protective equipment, first aid kits and waste disposal system. The data was analyzed using descriptive analysis with SPSS version16 statistical software. All of the respondents reported none of the hospital laboratories were labeled with the appropriate safety label and safety symbols. These respondents also reported they may contain organisms grouped under risk group IV in the absence of microbiological safety cabinets. Overall, the respondents reported that there were poor safety regulations or standards in their laboratories. There were higher risks of microbial, chemical and physical/mechanical hazards. Laboratory safety in public hospitals of Oromia Regional State is below the standard. The laboratory workers are at high risk of combined physical, chemical and microbial hazards. Prompt recognition of the problem and immediate action is mandatory to ensure safe working environment in health laboratories.

Does external evaluation of laboratories improve patient safety?

Science.gov (United States)

Noble, Michael A

2007-01-01

Laboratory accreditation and External Quality Assessment (also called proficiency testing) are mainstays of laboratory quality assessment and performance. Both practices are associated with examples of improved laboratory performance. The relationship between laboratory performance and improved patient safety is more difficult to assess because of the many variables that are involved with patient outcome. Despite this difficulty, the argument to continue external evaluation of laboratories is too compelling to consider the alternative.

Laboratory Directed Research and Development Program

International Nuclear Information System (INIS)

1994-02-01

This report is compiled from annual reports submitted by principal investigators following the close of fiscal year 1993. This report describes the projects supported and summarizes their accomplishments. The program advances the Laboratory's core competencies, foundations, scientific capability, and permits exploration of exciting new opportunities. Reports are given from the following divisions: Accelerator and Fusion Research, Chemical Sciences, Earth Sciences, Energy and Environment, Engineering, Environment -- Health and Safety, Information and Computing Sciences, Life Sciences, Materials Sciences, Nuclear Science, Physics, and Structural Biology

Summary of ORNL work on NRC-sponsored HTGR safety research, July 1974-September 1980

International Nuclear Information System (INIS)

Ball, S.J.; Cleveland, J.C.; Conklin, J.C.; Delene, J.G.; Harrington, R.M.; Hatta, M.; Hedrick, R.A.; Johnson, L.G.; Sanders, J.P.

1982-03-01

A summary is presented of the major accomplishments of the Oak Ridge National Laboratory (ORNL) research program on High-Temperature Gas-Cooled Reactor (HTGR) safety. This report is intended to help the nuclear Regulatory Commission establish goals for future research by comparing the status of the work here (as well as at other laboratories) with the perceived safety needs of the large HTGR. The ORNL program includes extensive work on dynamics-related safety code development, use of codes for studying postulated accident sequences, and use of experimental data for code verification. Cooperative efforts with other programs are also described. Suggestions for near-term and long-term research are presented

Nuclear safety research collaborations between the US and Russian Federation international nuclear safety centers

International Nuclear Information System (INIS)

Hill, D.J; Braun, J.C; Klickman, A.E.; Bugaenko, S.E; Kabanov, L.P; Kraev, A.G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the U.S. Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the U. S. Center at Argonne National Laboratory in October 1995. MINATOM established the Russian Center at the Research and Development Institute of Power Engineering in Moscow in July 1996. In April 1998 the Russian center became an independent, autonomous organization under MINATOM. The goals of the centers are to: cooperate in the development of technologies associated with nuclear safety in nuclear power engineering. be international centers for the collection of information important for safety and technical improvements in nuclear power engineering. maintain a base for fundamental knowledge needed to design nuclear reactors.The strategic approach that is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors

The Development of Laboratory Safety Questionnaire for Middle School Science Teachers

Science.gov (United States)

Akpullukcu, Simge; Cavas, Bulent

2017-01-01

The purpose of this paper is to develop a "valid and reliable laboratory safety questionnaire" which could be used to identify science teachers' understanding about laboratory safety issues during their science laboratory activities. The questionnaire was developed from a literature review and prior instruments developed on laboratory…

A 2-year study of patient safety competency assessment in 29 clinical laboratories.

Science.gov (United States)

Reed, Robyn C; Kim, Sara; Farquharson, Kara; Astion, Michael L

2008-06-01

Competency assessment is critical for laboratory operations and is mandated by the Clinical Laboratory Improvement Amendments of 1988. However, no previous reports describe methods for assessing competency in patient safety. We developed and implemented a Web-based tool to assess performance of 875 laboratory staff from 29 laboratories in patient safety. Question categories included workplace culture, categorizing error, prioritization of patient safety interventions, strength of specific interventions, and general patient safety concepts. The mean score was 85.0%, with individual scores ranging from 56% to 100% and scores by category from 81.3% to 88.6%. Of the most difficult questions (laboratory technologists. Computer-based competency assessments help laboratories identify topics for continuing education in patient safety.

Shaft extension design at the Underground Research Laboratory, Pinawa, Manitoba

International Nuclear Information System (INIS)

Kuzyk, G.W.; Ball, A.E.

1991-01-01

AECL Research has constructed an underground laboratory for the research and development required for the Canadian Nuclear Fuel Waste Management Program. The experimental program in the laboratory will contribute to the assessment of the feasibility and safety of nuclear fuel waste disposal deep in stable plutonic rock. In 1988, AECL extended the shaft of the Underground Research Laboratory (URL) from the existing 255 m depth to a depth of 443 m in cooperation with the United States Department of Energy. The project, which involved carrying out research activities while excavation and construction work was in progress, required careful planning. To accommodate the research programs, full-face blasting with a burn cut was used to advance the shaft. Existing facilities at the URL had to be modified to accommodate an expanded underground facility at a new depth. This paper discusses the design criteria, shaft-sinking methods and approaches used to accommodate the research work during this shaft extension project. (11 refs., 11 figs.)

Laboratory training manual on the use of nuclear techniques in pesticide research

International Nuclear Information System (INIS)

1983-01-01

This is a laboratory training manual on the use of nuclear techniques, and in particular radioisotopes in pesticide research. It is designed to give the scientists involved in pesticide research the basic terms and principles for understanding ionizing radiation: detection and measurement its hazards and safety measures, and some of the more common applications. Laboratory exercises representing the types of experiments that are valuable in pesticide research programmes and field tests which demonstrate the use of radiolabelled pesticides are included

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

Oak Ridge National Laboratory site data for safety-analysis report

International Nuclear Information System (INIS)

Fitzpatrick, F.C.

1982-12-01

The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs

Oak Ridge National Laboratory site data for safety-analysis report

Energy Technology Data Exchange (ETDEWEB)

Fitzpatrick, F.C.

1982-12-01

The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs.

The Horonobe Underground Research Laboratory (Tentative name) Project. A program on survey and research performed from earth surface

International Nuclear Information System (INIS)

2001-03-01

The Horonobe Underground Research Laboratory (Tentative name) Project under planning at Horonobe-machi by the Japan Nuclear Cycle Development Institute (JNC) is a research facility on deep underground shown in the Long-term program on research, development and application of nuclear energy (June, 1994)' (LPNE), where some researches on the deep underground targeted at sedimentary rocks are carried out. The plan on The Horonobe Underground Research Laboratory performed at Horonobe-machi' is an about 20 years plan ranging from beginning to finishing of its survey and research, which is carried out by three steps such as 'Survey and research performed from earth surface', 'Survey and research performed under excavation of road', and Survey and research performed by using the road'. The Horonobe Underground Research Laboratory is one of research facilities on deep underground shown its importance in LPNE, and carries out some researches on the deep underground at a target of the sedimentary rocks. And also The Horonobe Underground Research Laboratory confirms some technical reliability and support on stratum disposal shown in the 'Technical reliability on stratum disposal of the high level radioactive wastes. The Second Progress Report of R and D on geological disposal' summarized on November, 1999 by JNC through actual tests and researches at the deep stratum. The obtained results are intended to reflect to disposal business of The Horonobe Underground Research Laboratory and safety regulation and so on performed by the government, together with results of stratum science research, at the Tono Geoscience Center, of geological disposal R and D at the Tokai Works, or of international collaborations. For R and D at the The Horonobe Underground Research Laboratory after 2000, following subjects are shown: 1) Survey technique on long-term stability of geological environment, 2) Survey technique on geological environment, 3) Engineering technique on engineered barrier and

Evaluation of Hazardous Material Management Safety in the Chemical Laboratory in BATAN

International Nuclear Information System (INIS)

Nur-Rahmah-Hidayati

2005-01-01

The management safety of the hazardous material (B3) in the chemical laboratory of BATAN was evaluated. The evaluation is necessary to be done because B3 is often used together with radioactive materials in the laboratory, but the attention to the safety aspect of B3 is not paid sufficiently in spite of its big potential hazard. The potential hazard generated from the nature of B3 could be flammable, explosive, oxidative, corrosive and poisonous. The handling of B3 could be conducted by enforcing the labelling and classification in the usage and disposal processes. Some observations of the chemical laboratory of BATAN show that the management safety of hazardous material in compliance with the government regulation no. 74 year 2001 has not been dully conducted. The management safety of B3 could be improved by, designating one who has adequate skill in hazardous material safety specially as the B3 safety officer, providing the Material Safety Data Sheet that is updated periodically to use in the laboratory and storage room, updating periodically the inventory of B3, performing training in work safety periodically, and monitoring the ventilation system intensively in laboratory and storage room. (author)

Laboratory Safety Manual for Alabama Schools. Bulletin 1975. No. 20.

Science.gov (United States)

Alabama State Dept. of Education, Montgomery.

This document presents the Alabama State Department of Education guidelines for science laboratory safety, equipment, storage, chemical safety, rocket safety, electrical safety, safety with radioisotopes, and safety with biologicals. Also included is a brief bibliography, a teacher's checklist, a listing of laser facts and regulations, and a…

Laboratory Directed Research and Development Program FY2004

Energy Technology Data Exchange (ETDEWEB)

Hansen, Todd C.

2005-03-22

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Berkeley Lab's research and the Laboratory Directed Research and Development (LDRD) program support DOE's Strategic Goals that are codified in DOE's September 2003 Strategic Plan, with a primary focus on Advancing Scientific Understanding. For that goal, the Fiscal Year (FY) 2004 LDRD projects support every one of the eight strategies described in the plan. In addition, LDRD efforts support the goals of Investing in America's Energy Future (six of the fourteen strategies), Resolving the Environmental Legacy (four of the eight strategies), and Meeting National Security Challenges (unclassified fundamental research that supports stockpile safety and nonproliferation programs). The LDRD supports Office of Science strategic plans, including the 20 year Scientific Facilities Plan and the draft Office of Science Strategic Plan. The research also

Safety program of the Oak Ridge National Laboratory: a different approach

International Nuclear Information System (INIS)

Burger, G.H.

1981-01-01

The uniqueness and therefore different approach to Oak Ridge National Laboratory's safety program is not a result of elimination of the usual industrial safety organization, but results from the three organizations which supplement it and the areas of safety concerns that they cover. While industrial safety is primarily concerned with day-to-day routine worker activities (wearing of safety glasses and hard hats, adherence to electrical safety work procedures, proper safety lockout and tagout of equipment for maintenance activities, etc.), the other organizations, the Office of Operational Safety, Division Safety Officers and Radiation Control Officers, and the Laboratory director's Review Committees, are concerned with themuch broader spectrum of the total work environment. These organizations are concerned not only with the day-to-day worker activities but the design and conduction of all operations from a process viewpoint. The emphasis of these groups is assuring first that operations, experiments, facilities, etc., are designed properly and then secondly operated properly to assure safety of the operators, Laboratory population, and the public. Responsibilities of the three safety organizations constituting operational or process safety are described and discussed

Sandia Laboratories environment and safety programs

International Nuclear Information System (INIS)

Zak, B.D.; McGrath, P.E.; Trauth, C.A. Jr.

1975-01-01

Sandia, one of ERDA's largest laboratories, is primarily known for its extensive work in the nuclear weapons field. In recent years, however, Sandia's role has expanded to embrace sizeable programs in the energy, resource recovery, and the environment and safety fields. In this latter area, Sandia has programs which address nuclear, fossil fuel, and general environment and safety issues. Here we survey ongoing activities and describe in more detail aa few projects of particular interest. These range from a study of the impact of sealed disposal of radioactive wastes, through reactor safety and fossil fuel plume chemistry, to investigations of the composition and dynamics of the stratosphere

Proceedings of the research conference on post-accident waste management safety (RCWM2016) and the technical seminar on safety research for radioactive waste storage

International Nuclear Information System (INIS)

Motooka, Takafumi; Yamagishi, Isao

2017-03-01

Collaborative Laboratories for Advanced Decommissioning Science (CLADS) is responsible to promote international cooperation in the R and D activities on the decommissioning of Fukushima Daiichi Nuclear Power Station and to develop the necessary human resources. CLADS held the Research Conference on Post-accident Waste Management Safety (RCWM2016) on 7th November, 2016 and the Technical Seminar on Safety Research for Radioactive Waste Storage on 8th November, 2016. This report compiles the abstracts and the presentation materials in the above conference and seminar. (author)

Simula Research Laboratory

CERN Document Server

Tveito, Aslak

2010-01-01

The Simula Research Laboratory, located just outside Oslo in Norway, is rightly famed as a highly successful research facility, despite being, at only eight years old, a very young institution. This fascinating book tells the history of Simula, detailing the culture and values that have been the guiding principles of the laboratory throughout its existence. Dedicated to tackling scientific challenges of genuine social importance, the laboratory undertakes important research with long-term implications in networks, computing and software engineering, including specialist work in biomedical comp

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

International Nuclear Information System (INIS)

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

1996-03-01

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

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

Energy Technology Data Exchange (ETDEWEB)

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

1996-03-01

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

The impact of regulations, safety considerations and physical limitations on research progress at maximum biocontainment.

Science.gov (United States)

Shurtleff, Amy C; Garza, Nicole; Lackemeyer, Matthew; Carrion, Ricardo; Griffiths, Anthony; Patterson, Jean; Edwin, Samuel S; Bavari, Sina

2012-12-01

We describe herein, limitations on research at biosafety level 4 (BSL-4) containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT) are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP) conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review.

The Impact of Regulations, Safety Considerations and Physical Limitations on Research Progress at Maximum Biocontainment

Directory of Open Access Journals (Sweden)

Jean Patterson

2012-12-01

Full Text Available We describe herein, limitations on research at biosafety level 4 (BSL-4 containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review.

The Impact of Regulations, Safety Considerations and Physical Limitations on Research Progress at Maximum Biocontainment

Science.gov (United States)

Shurtleff, Amy C.; Garza, Nicole; Lackemeyer, Matthew; Carrion, Ricardo; Griffiths, Anthony; Patterson, Jean; Edwin, Samuel S.; Bavari, Sina

2012-01-01

We describe herein, limitations on research at biosafety level 4 (BSL-4) containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT) are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP) conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review. PMID:23342380

Oak Ridge National Laboratory Research Reactor Experimenters' Guide

International Nuclear Information System (INIS)

Cagle, C.D.

1982-10-01

The Oak Ridge National Laboratory has three multipurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the same safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to the intent of the experiment or quality of the data obtained. The necessity for, and the limitations of, the standards are discussed; and a compilation of general standards is included

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)

Laboratory Directed Research and Development Program, FY 1992

Energy Technology Data Exchange (ETDEWEB)

1993-01-01

This report is compiled from annual reports submitted by principal investigators following the close of the 1992 fiscal year. It describes the projects supported and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The Divisions that report include: Accelerator and Fusion Research, Chemical Sciences, Earth Sciences, Energy and Environment, Engineering, Environment and Safety and Health, Information and Computing Sciences, Life Sciences, Materials Sciences, Nuclear Science, Physics and Structural Biology.

Laboratory Directed Research and Development Program, FY 1992

International Nuclear Information System (INIS)

1993-01-01

This report is compiled from annual reports submitted by principal investigators following the close of the 1992 fiscal year. It describes the projects supported and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The Divisions that report include: Accelerator and Fusion Research, Chemical Sciences, Earth Sciences, Energy and Environment, Engineering, Environment and Safety and Health, Information and Computing Sciences, Life Sciences, Materials Sciences, Nuclear Science, Physics and Structural Biology

Guidelines for Biosafety Training Programs for Workers Assigned to BSL-3 Research Laboratories.

Science.gov (United States)

Homer, Lesley C; Alderman, T Scott; Blair, Heather Ann; Brocard, Anne-Sophie; Broussard, Elaine E; Ellis, Robert P; Frerotte, Jay; Low, Eleanor W; McCarthy, Travis R; McCormick, Jessica M; Newton, JeT'Aime M; Rogers, Francine C; Schlimgen, Ryan; Stabenow, Jennifer M; Stedman, Diann; Warfield, Cheryl; Ntiforo, Corrie A; Whetstone, Carol T; Zimmerman, Domenica; Barkley, Emmett

2013-03-01

The Guidelines for Biosafety Training Programs for Workers Assigned to BSL-3 Research Laboratories were developed by biosafety professionals who oversee training programs for the 2 national biocontainment laboratories (NBLs) and the 13 regional biocontainment laboratories (RBLs) that participate in the National Institute of Allergy and Infectious Diseases (NIAID) NBL/RBL Network. These guidelines provide a general training framework for biosafety level 3 (BSL-3) high-containment laboratories, identify key training concepts, and outline training methodologies designed to standardize base knowledge, understanding, and technical competence of laboratory personnel working in high-containment laboratories. Emphasis is placed on building a culture of risk assessment-based safety through competency training designed to enhance understanding and recognition of potential biological hazards as well as methods for controlling these hazards. These guidelines may be of value to other institutions and academic research laboratories that are developing biosafety training programs for BSL-3 research.

Current Sandia programs and laboratory facilities for tritium research

International Nuclear Information System (INIS)

Swansiger, W.A.; West, L.A.

1975-01-01

Currently envisioned fusion reactor systems will contain substantial quantities of tritium. Strict control of the overall tritium inventory and environmental safety considerations require an accurate knowledge of the behavior of this isotope in the presence of Controlled Thermonuclear Reactor (CTR) materials. A 14,000 ft 2 laboratory for tritium research is currently under construction at Sandia Laboratories in Livermore. Details about the laboratory in general are provided. Results from studies of hydrogen isotope diffusion in surface-characterized metals will be presented. Details of two permeation systems (one for hydrogen and deuterium, the other for tritium) will be discussed. Data will also be presented concerning the gettering of hydrogen isotopes and application to CTR collector designs. (auth)

Laboratory Directed Research and Development Program FY 2006

Energy Technology Data Exchange (ETDEWEB)

Hansen (Ed.), Todd

2007-03-08

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness.

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Henderson, B.D.; Meade, R.A.; Pruvost, N.L.

1999-01-01

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is a program jointly funded by the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) in conjunction with the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2. The goal of CSIRC is to preserve primary criticality safety documentation from U.S. critical experimental sites and to make this information available for the benefit of the technical community. Progress in archiving criticality safety primary documents at the LANL archives as well as efforts to make this information available to researchers are discussed. The CSIRC project has a natural linkage to the International Criticality Safety Benchmark Evaluation Project (ICSBEP). This paper raises the possibility that the CSIRC project will evolve in a fashion similar to the ICSBEP. Exploring the implications of linking the CSIRC to the international criticality safety community is the motivation for this paper

Status of electrical safety in Indira Gandhi Centre for Atomic Research

International Nuclear Information System (INIS)

Kandasamy, S.; Karthikeyan, S.V.; Senthilkumar, B.; Shunmugam, U.; Kannan, S.E.

1999-01-01

Electrical Systems in Indira Gandhi Centre for Atomic Research (IGCAR), comprising of facilities such as Fast Breeder Test Reactor (FBTR) and various Research and Development laboratories form a complex network providing practically uninterrupted power supply to all the facilities meeting their energy demands. The safety record of the Centre for the past 25 years has been very good and the number of electrical accidents in the Centre has been less. This paper brings out the status of the electrical safety in IGCAR and indicates the steps to be taken to improve the safety culture. It also utilizes the measure to be provided for improving the electrical safety in the works executed by contractors

Knowledge, attitude and practice of aspects of laboratory safety in Pathology Laboratories at the University of Port Harcourt Teaching Hospital, Nigeria.

Science.gov (United States)

Ejilemele, A A; Ojule, A C

2005-12-01

To assess current knowledge, attitudes and practice of aspects of laboratory safety in pathology laboratories at the University of Port Harcourt Teaching Hospital in view of perceived inadequacies in safety practices in clinical laboratories in developing countries. Sixty (60) self- administered questionnaires were distributed to all cadres of staff in four (4) different laboratories (Chemical Pathology, Haematology, Blood bank and Medical Microbiology) at the Hospital. Gross deficiencies were found in the knowledge, attitudes and practice of laboratory safety by laboratory staff in areas of use of personal protective equipment, specimen collection and processing, centrifuge--related hazards, infective hazards waste disposal and provision and use of First Aid Kits. Issues pertaining to laboratory safety are not yet given adequate attention by both employers and employees in developing countries in this ear of resurgence of diseases such as HIV/AIDS and Hepatitis Band C, is emphasized.

Nuclear criticality safety staff training and qualifications at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Monahan, S.P.; McLaughlin, T.P.

1997-01-01

Operations involving significant quantities of fissile material have been conducted at Los Alamos National Laboratory continuously since 1943. Until the advent of the Laboratory's Nuclear Criticality Safety Committee (NCSC) in 1957, line management had sole responsibility for controlling criticality risks. From 1957 until 1961, the NCSC was the Laboratory body which promulgated policy guidance as well as some technical guidance for specific operations. In 1961 the Laboratory created the position of Nuclear Criticality Safety Office (in addition to the NCSC). In 1980, Laboratory management moved the Criticality Safety Officer (and one other LACEF staff member who, by that time, was also working nearly full-time on criticality safety issues) into the Health Division office. Later that same year the Criticality Safety Group, H-6 (at that time) was created within H-Division, and staffed by these two individuals. The training and education of these individuals in the art of criticality safety was almost entirely self-regulated, depending heavily on technical interactions between each other, as well as NCSC, LACEF, operations, other facility, and broader criticality safety community personnel. Although the Los Alamos criticality safety group has grown both in size and formality of operations since 1980, the basic philosophy that a criticality specialist must be developed through mentoring and self motivation remains the same. Formally, this philosophy has been captured in an internal policy, document ''Conduct of Business in the Nuclear Criticality Safety Group.'' There are no short cuts or substitutes in the development of a criticality safety specialist. A person must have a self-motivated personality, excellent communications skills, a thorough understanding of the principals of neutron physics, a safety-conscious and helpful attitude, a good perspective of real risk, as well as a detailed understanding of process operations and credible upsets

Combustion Research Laboratory

Data.gov (United States)

Federal Laboratory Consortium — The Combustion Research Laboratory facilitates the development of new combustion systems or improves the operation of existing systems to meet the Army's mission for...

Handbook of laboratory health and safety measures

International Nuclear Information System (INIS)

Pal, S.B.

1985-01-01

Eighteen chapters deal with all kinds of possible health and safety hazards, chemical, physical and biological, arising in laboratories. Two chapters, on X-ray hazards - diagnostic and therapeutic, and radiation protection in radionuclide investigations, respectively are indexed separately. (U.K.)

Aquatic Research Laboratory (ARL)

Data.gov (United States)

Federal Laboratory Consortium — Columbia River and groundwater well water sources are delivered to the Aquatic Research Laboratory (ARL), where these resources are used to conduct research on fish...

Laboratory of research for environmental radiation and its dosimetry in the ININ

International Nuclear Information System (INIS)

Chavez S, B.M.

2003-01-01

The objectives of this work are to learn on the methodology that should be continued for the investigation of such a specialized topic as it is a radiation laboratory and to develop the executive project of a building that contains laboratories focused to the investigation of the radiation levels in the environment and their dosimetry. The National Institute of Nuclear Research (ININ), is the place where are carried out many of the investigations related to the field of the physics and chemistry in Mexico besides being the center of nuclear research more important of Latin America and it is for that reason that here is proposed the Laboratory of Low Radiation and its Dosimetry, since the Institute accounts with the whole infrastructure and necessary safety for this type of laboratories. (Author)

Progress report on safety research on radioactive waste management for the period April 1992 to March 1993

International Nuclear Information System (INIS)

Muraoka, Susumu; Senoo, Muneaki; Sekine, Keiichi

1994-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Shallow Land Migration Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. 2) In the safety evaluation study for shallow land disposal, migration behavior in the soil layer were studied. 3) In the safety evaluation study for geological disposal, chemical behavior of nuclide in water, nuclide migration and fixation in geosphere were studied. 4) Distribution of uranium and migration of uranium series nuclide in uranium ore were examined as a natural analogue study. (author)

The safety evaluation guide for laboratories and plants a tool for enhancing safety

International Nuclear Information System (INIS)

Lhomme, Veronique; Daubard, Jean-Paul

2013-01-01

The Institute for Radioprotection and Nuclear Safety (IRSN) acts as technical support for the French government Authorities competent in nuclear safety and radiation protection for civil and defence activities. In this frame, the Institute's performs safety assessments of the safety cases submitted by operators to these Authorities for each stage in the life cycle of a nuclear facility, including dismantling operations, which is subjected to a licensing procedure. In the fuel cycle field, this concerns a large variety of facilities. Very often, depending on facilities and on safety cases, safety assessment to be performed is multidisciplinary and involves the supervisor in charge of the facility and several safety experts, particularly to cover the whole set of risks (criticality, exposure to radiation, fire, handling, containment, human and organisational factors...) encountered during facility's operations. Taking these into account, and in order to formalize the assessment process of the fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management, the 'Plants, Laboratories, Transports and Waste Safety' Division of IRSN has developed an internal guide, as a tool: - To present the methodological framework, and possible specificities, for the assessment according to the 'Defence in Depth Concept' (Part 1); - To provide key questions associated to the necessary contradictory technical review of the safety cases (Part 2); - To capitalise on experience on the basis of technical examples (coming from incident reports, previous safety assessments...) demonstrating the questioning (Part 3). The guide is divided in chapters, each dedicated to a type of risk (dissemination of radioactive material, external or internal exposure from ionising radiation, criticality, radiolysis mechanisms, handling operations, earthquake, human or organisational factors...) or to a type

Safety Precautions and Operating Procedures in an (A)BSL-4 Laboratory: 1. Biosafety Level 4 Suit Laboratory Suite Entry and Exit Procedures.

Science.gov (United States)

Janosko, Krisztina; Holbrook, Michael R; Adams, Ricky; Barr, Jason; Bollinger, Laura; Newton, Je T'aime; Ntiforo, Corrie; Coe, Linda; Wada, Jiro; Pusl, Daniela; Jahrling, Peter B; Kuhn, Jens H; Lackemeyer, Matthew G

2016-10-03

Biosafety level 4 (BSL-4) suit laboratories are specifically designed to study high-consequence pathogens for which neither infection prophylaxes nor treatment options exist. The hallmarks of these laboratories are: custom-designed airtight doors, dedicated supply and exhaust airflow systems, a negative-pressure environment, and mandatory use of positive-pressure ("space") suits. The risk for laboratory specialists working with highly pathogenic agents is minimized through rigorous training and adherence to stringent safety protocols and standard operating procedures. Researchers perform the majority of their work in BSL-2 laboratories and switch to BSL-4 suit laboratories when work with a high-consequence pathogen is required. Collaborators and scientists considering BSL-4 projects should be aware of the challenges associated with BSL-4 research both in terms of experimental technical limitations in BSL-4 laboratory space and the increased duration of such experiments. Tasks such as entering and exiting the BSL-4 suit laboratories are considerably more complex and time-consuming compared to BSL-2 and BSL-3 laboratories. The focus of this particular article is to address basic biosafety concerns and describe the entrance and exit procedures for the BSL-4 laboratory at the NIH/NIAID Integrated Research Facility at Fort Detrick. Such procedures include checking external systems that support the BSL-4 laboratory, and inspecting and donning positive-pressure suits, entering the laboratory, moving through air pressure-resistant doors, and connecting to air-supply hoses. We will also discuss moving within and exiting the BSL-4 suit laboratories, including using the chemical shower and removing and storing positive-pressure suits.

Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

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

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

Geometric Design Laboratory

Data.gov (United States)

Federal Laboratory Consortium — Purpose: The mission of the Geometric Design Laboratory (GDL) is to support the Office of Safety Research and Development in research related to the geometric design...

Restructuring of University Laboratories within the Scope of Occupational Health and Safety

OpenAIRE

Ordu, Kamil Musa; Çivi Bilir, Gülçin

2018-01-01

Laboratory safety is major of importance tooccupational health and safety, which manages, and responds to all issues andconcerns surrounding physical, biological, ergonomic, electrical, chemical, andother standard operating procedures. In this work, laboratory design and equipment,which are arranged according to precautions that are taken against to allhazards regarding to work environment or personal expose at the workenvironments in laboratories that are already exist or will be established...

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

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

International Nuclear Information System (INIS)

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

1989-02-01

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

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

Cryptosporidiosis outbreak at an academic animal research laboratory-Colorado, 2014.

Science.gov (United States)

Hancock-Allen, Jessica; Alden, Nisha B; Cronquist, Alicia B

2017-02-01

After cryptosporidiosis was reported in three workers caring for preweaned calves at an academic research laboratory, we sought to identify cases, determine risk factors, and implement control measures. A cryptosporidiosis case was defined as diarrhea duration ≥72 hr, abdominal cramps, or vomiting in an animal research laboratory worker during July 14-July 31. A confirmed case had laboratory evidence of Cryptosporidium infection. Staff were interviewed regarding illness, potential exposures, training, and personal protective equipment (PPE) standard operating procedures (SOPs). The cryptosporidiosis attack rate (AR) was 74% (20/27); five were laboratory-confirmed. Median job training was 2 hr including respiratory-fit testing. No SOPs existed for doffing PPE. AR for workers who removed their gloves first was 84% (16/19) compared with 20% (1/5) for workers who removed gloves last (risk ratio = 4.2; P importance of adequate training, enforced proper PPE procedures, and promoting a culture of safety. Am. J. Ind. Med. 60:208-214, 2017. © 2017 Wiley Periodicals, Inc. © 2017 Wiley Periodicals, Inc.

Current status of international cooperation on nuclear safety research

International Nuclear Information System (INIS)

Katsuragi, Satoru

1984-01-01

JAERI (Japan Atomic Energy Research Institute), as a representative organization in Japan, has been participating in many international cooperations on nuclear safety research. This report reviews the recent achievement and evolution of the international cooperative safety studies. Twelve projects that are based on the agreements between JAERI and foreign organizations are reviewed. As the fuel irradiation studies, the recent achievement of the OECD Halden Reactor Project and the agreement between Pacific Northwest Laboratories, Battelle Memorial Institute, and JAERI are explained. As for the study of reactivity accident, the cooperation of the NSRR (Nuclear Safety Research Reactor) project in Japan with PBF, PNS and PHEBUS projects in the U.S., West Germany and France, respectively, are now in progress. The fuel performance in abnormal transient and the experiment and analysis of severe fuel damage are the new areas of international interest. The OECD/LOFT project and ROSA-4 projects are also explained in connection with the FP source term problem and the analysis codes such as RELAP-5 and TRAC. As the safety studies associated with the downstream of the nuclear fuel cycle, the BEFAST project of IAEA and the ISIRS project of OECD/NEA are shortly reviewed. (Aoki, K.)

Spent fuel reprocessing and minor actinide partitioning safety related research at the UK National Nuclear Laboratory

International Nuclear Information System (INIS)

Carrott, Michael; Flint, Lauren; Gregson, Colin; Griffiths, Tamara; Hodgson, Zara; Maher, Chris; Mason, Chris; McLachlan, Fiona; Orr, Robin; Reilly, Stacey; Rhodes, Chris; Sarsfield, Mark; Sims, Howard; Shepherd, Daniel; Taylor, Robin; Webb, Kevin; Woodall, Sean; Woodhead, David

2015-01-01

The development of advanced separation processes for spent nuclear fuel reprocessing and minor actinide recycling is an essential component of international R and D programmes aimed at closing the nuclear fuel cycle around the middle of this century. While both aqueous and pyrochemical processes are under consideration internationally, neither option will gain broad acceptance without significant advances in process safety, waste minimisation, environmental impact and proliferation resistance; at least when compared to current reprocessing technologies. The UK National Nuclear Laboratory (NNL) is developing flowsheets for innovative aqueous separation processes. These include advanced PUREX options (i.e. processes using tributyl phosphate as the extractant for uranium, plutonium and possibly neptunium recovery) and GANEX (grouped actinide extraction) type processes that use diglycolamide based extractants to co-extract all transuranic actinides. At NNL, development of the flowsheets is closely linked to research on process safety, since this is essential for assessing prospects for future industrialisation and deployment. Within this context, NNL is part of European 7. Framework projects 'ASGARD' and 'SACSESS'. Key topics under investigation include: hydrogen generation from aqueous and solvent phases; decomposition of aqueous phase ligands used in separations prior to product finishing and recycle of nitric acid; dissolution of carbide fuels including management of organics generated. Additionally, there is a strong focus on use of predictive process modelling to assess flowsheet sensitivities as well as engineering design and global hazard assessment of these new processes. (authors)

Planning an Automatic Fire Detection, Alarm, and Extinguishing System for Research Laboratories

Directory of Open Access Journals (Sweden)

Rostam Golmohamadi

2014-04-01

Full Text Available Background & Objectives: Educational and research laboratories in universities have a high risk of fire, because they have a variety of materials and equipment. The aim of this study was to provide a technical plan for safety improvement in educational and research laboratories of a university based on the design of automatic detection, alarm, and extinguishing systems . Methods : In this study, fire risk assessment was performed based on the standard of Military Risk Assessment method (MIL-STD-882. For all laboratories, detection and fire alarm systems and optimal fixed fire extinguishing systems were designed. Results : Maximum and minimum risks of fire were in chemical water and wastewater (81.2% and physical agents (62.5% laboratories, respectively. For studied laboratories, we designed fire detection systems based on heat and smoke detectors. Also in these places, fire-extinguishing systems based on CO2 were designed . Conclusion : Due to high risk of fire in studied laboratories, the best control method for fire prevention and protection based on special features of these laboratories is using automatic detection, warning and fire extinguishing systems using CO2 .

Safety leadership in the teaching laboratories of electrical and electronic engineering departments at Taiwanese Universities.

Science.gov (United States)

Wu, Tsung-Chih

2008-01-01

Safety has always been one of the principal goals in teaching laboratories. Laboratories cannot serve their educational purpose when accidents occur. The leadership of department heads has a major impact on laboratory safety, so this study discusses the factors affecting safety leadership in teaching laboratories. This study uses a mail survey to explore the perceived safety leadership in electrical and electronic engineering departments at Taiwanese universities. An exploratory factor analysis shows that there are three main components of safety leadership, as measured on a safety leadership scale: safety controlling, safety coaching, and safety caring. The descriptive statistics also reveals that among faculty, the perception of department heads' safety leadership is in general positive. A two-way MANOVA shows that there are interaction effects on safety leadership between university size and instructor age; there are also interaction effects between presence of a safety committee and faculty gender and faculty age. It is therefore necessary to assess organizational factors when determining whether individual factors are the cause of differing perceptions among faculty members. The author also presents advice on improving safety leadership for department heads at small universities and at universities without safety committees.

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

Energy Technology Data Exchange (ETDEWEB)

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

1989-02-01

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

Zoonoses of occupational health importance in contemporary laboratory animal research.

Science.gov (United States)

Hankenson, F Claire; Johnston, Nancy A; Weigler, Benjamin J; Di Giacomo, Ronald F

2003-12-01

In contemporary laboratory animal facilities, workplace exposure to zoonotic pathogens, agents transmitted to humans from vertebrate animals or their tissues, is an occupational hazard. The primary (e.g., macaques, pigs, dogs, rabbits, mice, and rats) and secondary species (e.g., sheep, goats, cats, ferrets, and pigeons) of animals commonly used in biomedical research, as classified by the American College of Laboratory Animal Medicine, are established or potential hosts for a large number of zoonotic agents. Diseases included in this review are principally those wherein a risk to biomedical facility personnel has been documented by published reports of human cases in laboratory animal research settings, or under reasonably similar circumstances. Diseases are listed alphabetically, and each section includes information about clinical disease, transmission, occurrence, and prevention in animal reservoir species and humans. Our goal is to provide a resource for veterinarians, health-care professionals, technical staff, and administrators that will assist in the design and on-going evaluation of institutional occupational health and safety programs.

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.

Progress report on safety research on radioactive waste management for the period April 1995 to March 1996

International Nuclear Information System (INIS)

Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka

1997-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms. 2) In the safety evaluation study for shallow land disposal, migration behavior of radionuclides in a soil layer was studied. 3) In the safety evaluation study for geological disposal, chemical behavior of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analog study. (author)

Research and Progress on Virtual Cloud Laboratory

OpenAIRE

Zhang Jian Wei; Shang Zhi Hui; Yuan Chen; Ma Lin Lin; Cai Zeng Yu; Hu Chun Hui

2016-01-01

In recent years, cloud computing technology has experienced continuous development and improvement, and has gradually expanded to the education sector. First, this paper will introduce the background knowledge of the current virtual cloud laboratory; by comparing the advantages and disadvantages between traditional laboratory and virtual cloud laboratory, and comparing the application, advantages and disadvantages, and development trend of OpenStack technology and VMWare technology in safety,...

NASA's Propulsion Research Laboratory

Science.gov (United States)

2004-01-01

The grand opening of NASA's new, world-class laboratory for research into future space transportation technologies located at the Marshall Space Flight Center (MSFC) in Huntsville, Alabama, took place in July 2004. The state-of-the-art Propulsion Research Laboratory (PRL) serves as a leading national resource for advanced space propulsion research. Its purpose is to conduct research that will lead to the creation and development of innovative propulsion technologies for space exploration. The facility is the epicenter of the effort to move the U.S. space program beyond the confines of conventional chemical propulsion into an era of greatly improved access to space and rapid transit throughout the solar system. The laboratory is designed to accommodate researchers from across the United States, including scientists and engineers from NASA, the Department of Defense, the Department of Energy, universities, and industry. The facility, with 66,000 square feet of useable laboratory space, features a high degree of experimental capability. Its flexibility allows it to address a broad range of propulsion technologies and concepts, such as plasma, electromagnetic, thermodynamic, and propellant propulsion. An important area of emphasis is the development and utilization of advanced energy sources, including highly energetic chemical reactions, solar energy, and processes based on fission, fusion, and antimatter. The Propulsion Research Laboratory is vital for developing the advanced propulsion technologies needed to open up the space frontier, and sets the stage of research that could revolutionize space transportation for a broad range of applications.

Guidelines for euthanasia of laboratory animals used in biomedical research

Directory of Open Access Journals (Sweden)

Adina Baias,

2012-06-01

Full Text Available Laboratory animals are used in several fields of science research, especially in biology, medicine and veterinary medicine. The majority of laboratory animals used in research are experimental models that replace the human body in study regarding pharmacological or biological safety products, studies conducted for a betterunderstanding of oncologic processes, toxicology, genetic studies or even new surgical techniques. Experimental protocols include a stage in which animals are euthanized in order to remove organs and tissues,or for no unnecessary pain and suffering of animals (humane endpoints or to mark the end of research. The result of euthanasia techniques is a rapid loss of consciousness followed by cardiac arrest, respiratory arrest and disruption of brain activity. Nowadays, the accepted euthanasia techniques can use chemicals (inhalant agents like: carbon dioxide, nitrogen or argon, overdoses of injectable anesthetics or physical methods (decapitation, cervical spine dislocation, stunning, gunshot, pitching.

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)

Code of practice for safety in laboratory - non ionising radiation

International Nuclear Information System (INIS)

Ramli Jaya; Mohd Yusof Mohd Ali; Khoo Boo Huat; Khatijah Hashim

1995-01-01

The code identifies the non-ionizing radiation encountered in laboratories and the associated hazards. The code is intended as a laboratory standard reference document for general information on safety requirements relating to the usage of non-ionizing radiations in laboratories. The nonionizing radiations cover in this code, namely, are ultraviolet radiation, visible light, radio-frequency radiation, lasers, sound waves and ultrasonic radiation. (author)

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.)

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).

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)

Research program on nuclear technology and nuclear safety; Forschungsprogramm Kerntechnik und Nukleare Sicherheit - Synthesebericht 2009 des BFE-Programmleiters

Energy Technology Data Exchange (ETDEWEB)

Dreier, J.

2010-04-15

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 nuclear technology and nuclear safety. Work carried out, knowledge gained and results obtained in the various areas are reported on. These include projects carried out in the Laboratory for Reactor Physics and System Behaviour LRS, the LTH Thermohydraulics Laboratory, the Laboratory for Nuclear Materials LNM, the Laboratory for Final Storage Safety LES and the Laboratory for Energy Systems Analysis LEA of the Paul Scherrer Institute PSI. Work done in 2009 and results obtained are reported on, including research on transients in Swiss reactors, risk and human reliability. Work on the 'Proteus' research reactor is reported on, as is work done on component safety. International co-operation in the area of serious accidents and the disposal of nuclear wastes is reported on. Future concepts for reactors and plant life management are discussed. The energy business in general is also discussed. Finally, national and international co-operation is noted and work to be done in 2010 is reviewed.

Progress report on safety research on radioactive waste management for the period April 1993 to March 1995

Energy Technology Data Exchange (ETDEWEB)

Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [eds.

1996-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal years of 1993 and 1994 (April 1, 1993 - March 31, 1995). The topics are as follows: (1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. (2) In the safety evaluation study for shallow land disposal, migration behaviour of nuclides in the soil layer was studied. (3) In the safety evaluation study for geological disposal, chemical behaviour of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analogue study. (author).

Progress report on safety research on radioactive waste management for the period April 1993 to March 1995

International Nuclear Information System (INIS)

Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka

1996-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal years of 1993 and 1994 (April 1, 1993 - March 31, 1995). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. 2) In the safety evaluation study for shallow land disposal, migration behaviour of nuclides in the soil layer was studied. 3) In the safety evaluation study for geological disposal, chemical behaviour of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analogue study. (author)

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)

Energy Materials Research Laboratory (EMRL)

Data.gov (United States)

Federal Laboratory Consortium — The Energy Materials Research Laboratory at the Savannah River National Laboratory (SRNL) creates a cross-disciplinary laboratory facility that lends itself to the...

Knowledge, attitude and practice of aspects of laboratory safety in ...

African Journals Online (AJOL)

Result: Gross deficiencies were found in the knowledge, attitudes and practice of laboratory safety by laboratory staff in areas of use of personal protective equipment, specimen collection and processing, centrifuge – related hazards, infective hazards waste disposal and provision and use of First Aid Kits. Conclusion: ...

Small-Engine Research Laboratory (SERL)

Data.gov (United States)

Federal Laboratory Consortium — Description: The Small-Engine Research Laboratory (SERL) is a facility designed to conduct experimental small-scale propulsion and power generation systems research....

Safety system upgrades to a research reactor: A regulatory perspective

International Nuclear Information System (INIS)

Lamarre, G.B.; Martin, W.G.

2003-01-01

The NRU (National Research Universal) reactor, located at the Chalk River Laboratories of Atomic Energy of Canada Limited (AECL), first achieved criticality November 3, 1957. AECL continues to operate NRU for research to support safety and reliability studies for CANDU reactors and as a major supplier of medical radioisotopes. Following a detailed systematic review and assessment of NRU's design and the condition of its primary systems, AECL formally notified the Canadian Nuclear Safety Commission's (CNSC) predecessor - the Atomic Energy Control Board - in 1992 of its intention to upgrade NRU's safety systems. AECL proposed seven major upgrades to provide improvements in shutdown capability, heat removal, confinement, and reactor monitoring, particularly during and after a seismic event. From a CNSC perspective, these upgrades were necessary to meet modern safety standards. From the start of the upgrades project, the CNSC provided regulatory oversight aimed at ensuring that AECL maintained a structured approach to the upgrades. The elements of the approach include, but are not limited to, the determination of project milestones and target dates; the formalization of the design process and project quality assurance requirements; the requirements for updated documentation, including safety reports, safety notes and commissioning reports; and the approval and authorization process. This paper details, from a regulatory perspective, the structured approach used in approving the design, construction, commissioning and subsequent operation of safety system upgrades for an existing and operating research reactor, including the many challenges faced when attempting to balance the requirements of the upgrades project with AECL's need to keep NRU operating to meet its important research and production objectives. (author)

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

Research Combustion Laboratory (RCL)

Data.gov (United States)

Federal Laboratory Consortium — The Research Combustion Laboratory (RCL) develops aerospace propulsion technology by performing tests on propulsion components and materials. Altitudes up to 137,000...

[Validation of a questionnaire to evaluate patient safety in clinical laboratories].

Science.gov (United States)

Giménez Marín, Ángeles; Rivas-Ruiz, Francisco

2012-01-01

The aim of this study was to prepare, pilot and validate a questionnaire to evaluate patient safety in the specific context of clinical laboratories. A specific questionnaire on patient safety in the laboratory, with 62 items grouped into six areas, was developed, taking into consideration the diverse human and laboratory contextual factors which may contribute to producing errors. A pilot study of 30 interviews was carried out, including validity and reliability analyses using principal components factor analysis and Cronbach's alpha. Subsequently, 240 questionnaires were sent to 21 hospitals, followed by a test-retest of 41 questionnaires with the definitive version. The sample analyzed was composed of 225 questionnaires (an overall response rate of 80%). Of the 62 items initially assessed, 17 were eliminated due to non-compliance with the criteria established before the principal components factor analysis was performed. For the 45 remaining items, 12 components were identified, with an cumulative variance of 69.5%. In seven of the 10 components with two or more items, Cronbach's alpha was higher than 0.7. The questionnaire items assessed in the test-retest were found to be stable. We present the first questionnaire with sufficiently proven validity and reliability for evaluating patient safety in the specific context of clinical laboratories. This questionnaire provides a useful instrument to perform a subsequent macrostudy of hospital clinical laboratories in Spain. The questionnaire can also be used to monitor and promote commitment to patient safety within the search for continuous quality improvement. Copyright © 2011 SESPAS. Published by Elsevier Espana. All rights reserved.

Psychometric model for safety culture assessment in nuclear research facilities

Energy Technology Data Exchange (ETDEWEB)

Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

2017-04-01

Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

Psychometric model for safety culture assessment in nuclear research facilities

International Nuclear Information System (INIS)

Nascimento, C.S. do; Andrade, D.A.; Mesquita, R.N. de

2017-01-01

Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

Understanding safety data sheets as a strategy to protect humans and the environment at the laboratory

Science.gov (United States)

Elza, Rizkiawalia; Suherman, Suherman

2018-02-01

Safety Data Sheet (SDS) gave important information for safe chemicals handling and widely used in communicating chemical hazards. Laboratory as one of the places associated with the consumption of a number of chemicals, then the worker in laboratory have to know the information chemicals used. The purpose of this research is to know the perception and understanding of workers in a laboratory toward SDS. The quantitative research was used and the collect data by questionnaire using Likert scale, then analyzed descriptively. The total sample of data was twenty-seven of laboratory worker people. The finding from this study showed that a great majority of people agree SDS has benefits for workers in the laboratory, agree the SDS should be available in the workplace, feel the need to know the contents of the SDS, but not so many people agree `I access SDS while working using chemicals' and great majority of people feel `I obtained chemical information other than SDS'.

Understanding safety data sheets as a strategy to protect humans and the environment at the laboratory

Directory of Open Access Journals (Sweden)

Elza Rizkiawalia

2018-01-01

Full Text Available Safety Data Sheet (SDS gave important information for safe chemicals handling and widely used in communicating chemical hazards. Laboratory as one of the places associated with the consumption of a number of chemicals, then the worker in laboratory have to know the information chemicals used. The purpose of this research is to know the perception and understanding of workers in a laboratory toward SDS. The quantitative research was used and the collect data by questionnaire using Likert scale, then analyzed descriptively. The total sample of data was twenty-seven of laboratory worker people. The finding from this study showed that a great majority of people agree SDS has benefits for workers in the laboratory, agree the SDS should be available in the workplace, feel the need to know the contents of the SDS, but not so many people agree ‘I access SDS while working using chemicals’ and great majority of people feel ‘I obtained chemical information other than SDS’.

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

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.)

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.

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.

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

GRS' research on clay rock in the Mont Terri underground laboratory

Energy Technology Data Exchange (ETDEWEB)

Wieczorek, Klaus; Czaikowski, Oliver [Gesellschaft fuer Anlagen- und Reaktorsicherheit gGmbH, Braunschweig (Germany)

2016-07-15

For constructing a nuclear waste repository and for ensuring the safety requirements are met over very long time periods, thorough knowledge about the safety-relevant processes occurring in the coupled system of waste containers, engineered barriers, and the host rock is indispensable. For respectively targeted research work, the Mont Terri rock laboratory is a unique facility where repository research is performed in a clay rock environment. It is run by 16 international partners, and a great variety of questions are investigated. Some of the work which GRS as one of the Mont Terri partners is involved in is presented in this article. The focus is on thermal, hydraulic and mechanical behaviour of host rock and/or engineered barriers.

Laboratory Safety Needs of Kentucky School-Based Agricultural Mechanics Teachers

Science.gov (United States)

Saucier, P. Ryan; Vincent, Stacy K.; Anderson, Ryan G.

2014-01-01

The frequency and severity of accidents that occur in the agricultural mechanics laboratory can be reduced when these facilities are managed by educators who are competent in the area of laboratory safety and facility management (McKim & Saucier, 2011). To ensure teachers are technically competent and prepared to manage an agricultural…

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)

Habits of Mind for the Science Laboratory: Establishing Proper Safety Habits in the Laboratory Will Help Minimize the Risk of Accidents

Science.gov (United States)

Hayes, Lisa; Smith, Margaret; Eick, Charles

2005-01-01

Lab safety begins with the teacher. Teachers must make learning how to be safe an integral and important part of their professional development and work. Teachers who are unfamiliar with laboratory instruction should take whatever steps necessary to prepare for the unique challenges associated with safety in conducting laboratory investigations…

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

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1982-07-01

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

The Safety and Tritium Applied Research (STAR) Facility: Status-2004

International Nuclear Information System (INIS)

Anderl, R.A.; Longhurst, G.R.; Pawelko, R.J.; Sharpe, J.P.; Schuetz, S.T.; Petti, D.A.

2005-01-01

The Safety and Tritium Applied Research (STAR) Facility, a US DOE National User Facility at the Idaho National Engineering and Environmental Laboratory (INEEL), comprises capabilities and infrastructure to support both tritium and non-tritium research activities important to the development of safe and environmentally friendly fusion energy. Research thrusts include (1) interactions of tritium and deuterium with plasma-facing-component (PFC) materials, (2) fusion safety issues [PFC material chemical reactivity and dust/debris generation, activation product mobilization, tritium behavior in fusion systems], and (3) molten salts and fusion liquids for tritium breeder and coolant applications. This paper updates the status of STAR and the capabilities for ongoing research activities, with an emphasis on the development, testing and integration of the infrastructure to support tritium research activities. Key elements of this infrastructure include a tritium storage and assay system, a tritium cleanup system to process glovebox and experiment tritiated effluent gases, and facility tritium monitoring systems

Horonobe Underground Research Laboratory project. Investigation report for the 2010 fiscal year

International Nuclear Information System (INIS)

Nakayama, Masashi; Sawada, Sumiyuki; Sugita, Yutaka

2011-09-01

The Horonobe Underground Research Laboratory Project is planned to extend over a period 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2010 fiscal year (2010/2011). The investigations, which are composed of 'Geoscientific research' and 'R and D on geological disposal technology', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2010 Fiscal year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. For the sake of this, JAEA has proceeded with the project in collaboration with experts from domestic and overseas research organisations. (author)

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

International Nuclear Information System (INIS)

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

1997-01-01

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

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.

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

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.)

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)

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

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

Operational safety at the radiometallurgy laboratory of Fontenay-aux-Roses

International Nuclear Information System (INIS)

Hayet, Lucien; Petit, Pierre; Conche, Roger.

1976-01-01

Opened in 1967, the Radiometallurgy Laboratory is responsible for the examination of plutonium 239 based nuclear fuels of breeder reactors such as Rapsodie and Phenix. Part of the same laboratory is also responsible for the manufacture of californium 252 sources. These neutron sources can have a neutron fluency yield of 2,3 10 10 n/s/4π (i.e. 10mg of 252cf). This large laboratory includes a total area of 117m 2 of hot surfaces. It also includes 14 high activity cells with a capacity of 100000Ci at 1MeV. Located only 7km from the center of Paris, it must incorporate a special design and a particularly sure safety policy. Several statistics are given: irradiations, contaminations, incidents, quantity of fissile material, solid and liquid wastes etc... The principles of safety management are outlined and an analysis given of this basic nuclear facility [fr

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)

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)

Safety analysis report upgrade program at the Plutonium Facility, Los Alamos National Laboratory

International Nuclear Information System (INIS)

Pan, P.Y.

1993-01-01

Plutonium research and development activities have resided at the Los Alamos National Laboratory (LANL) since 1943. The function of the Plutonium Facility (PF-4) has been to perform basic special nuclear materials research and development and to support national defense and energy programs. The original Final Safety Analysis Report (FSAR) for PF-4 was approved by DOE in 1978. This FSAR analyzed design-basis and bounding accidents. In 1986, DOE/AL published DOE/AL Order 5481.1B, ''Safety Analysis and Review System'', as a requirement for preparation and review of safety analyses. To meet the new DOE requirements, the Facilities Management Group of the Nuclear Material Technology Division submitted a draft FSAR to DOE for approval in April 1991. This draft FSAR analyzed the new configurations and used a limited-scope probabilistic risk analysis for accident analysis. During the DOE review of the draft FSAR, DOE Order 5480.23 ''Nuclear Safety Analysis Reports'', was promulgated and was later officially released in April 1992. The new order significantly expands the scope, preparation, and maintenance efforts beyond those required in DOE/AL Order 5481.1B by requiring: description of institutional and human-factor safety programs; clear definitions of all facility-specific safety commitments; more comprehensive and detailed hazard assessment; use of new safety analysis methods; and annual updates of FSARs. This paper describes the safety analysis report (SAR) upgrade program at the Plutonium Facility in LANL. The SAR upgrade program is established to meet the requirements in DOE Order 5480.23. Described in this paper are the SAR background, authorization basis for operations, hazard classification, and technical program elements

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)

Progress report on safety research on high-level waste management for the period April 1989 to March 1990

International Nuclear Information System (INIS)

Muraoka, Susumu; Senoo, Muneaki; Kobayashi, Yoshii

1991-02-01

Research on high-level waste management at the Engineered Barrier Materials Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research, JAERI in the fiscal year of 1989 are described. The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies on glass and ceramic forms, and corrosion test of carbon steel were continued. 2) In the safety evaluation study for geological disposal, chemical behavior of nuclide in water, nuclide migration and retardation in geosphere were studied. New microspectrometers was developed to analyze the chemical form in rocks. 3) Distribution and migration of uranium in uranium ore were examined as a natural analogue study. (author)

Progress report on safety research on high-level waste management for the period April 1991 to March 1992

International Nuclear Information System (INIS)

Muraoka, Susumu; Senoo, Muneaki; Kobayashi, Yoshii

1993-03-01

Research on high-level waste management at the Engineered Barrier Materials Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research, JAERI in the fiscal year of 1991 are described. The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies on glass, ceramic and buffer materials were carried out. 2) In the safety evaluation study for geological disposal, behavior of radionuclide in deep underground water, nuclide migration in-situ and natural groundwater flow system were studied. 3) Changes in layer charge of smectite, alteration of uranium mineral and uranium fixation in uranium ore were examined as a natural analogue study. (author)

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

Presentation of the Nirex disposal safety research programme

International Nuclear Information System (INIS)

1988-01-01

Implementation of Nirex plans for the disposal of solid low and intermediate level radioactive waste deep underground requires assurances of safety at every stage. This includes assessment of long-term safety, which must be based on an understanding of how the repository and its contents will behave far into the future. This understanding is being provided by the company's substantial disposal research and development programme, currently running at a level of more than Pound 5 million annually. The principal contractor for the work is the UKAEA's Harwell Laboratory, with contributions from experts in universities and industry. Information from other national and international programmes also contributes. This document supports a presentation held at the CEGB Conference Centre, Didcot Power Station, Oxfordshire on 1st November 1988 to outline the scope of the work and its objectives in the context of the Company's plans and the requirements of safety assessments. It summarises the results and understanding being obtained from the current programme. (author)

Laboratory Directed Research and Development Program FY 2008 Annual Report

Energy Technology Data Exchange (ETDEWEB)

editor, Todd C Hansen

2009-02-23

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Berkeley Lab's research and the Laboratory Directed Research and Development (LDRD) program support DOE's Strategic Themes that are codified in DOE's 2006 Strategic Plan (DOE/CF-0010), with a primary focus on Scientific Discovery and Innovation. For that strategic theme, the Fiscal Year (FY) 2008 LDRD projects support each one of the three goals through multiple strategies described in the plan. In addition, LDRD efforts support the four goals of Energy Security, the two goals of Environmental Responsibility, and Nuclear Security (unclassified fundamental research that supports stockpile safety and nonproliferation programs). The LDRD program supports Office of Science strategic plans, including the 20-year Scientific Facilities Plan and the Office of Science Strategic Plan. The research also supports the strategic directions periodically under

Laboratory Directed Research and Development Program FY 2008 Annual Report

International Nuclear Information System (INIS)

Hansen, Todd C.

2009-01-01

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Berkeley Lab's research and the Laboratory Directed Research and Development (LDRD) program support DOE's Strategic Themes that are codified in DOE's 2006 Strategic Plan (DOE/CF-0010), with a primary focus on Scientific Discovery and Innovation. For that strategic theme, the Fiscal Year (FY) 2008 LDRD projects support each one of the three goals through multiple strategies described in the plan. In addition, LDRD efforts support the four goals of Energy Security, the two goals of Environmental Responsibility, and Nuclear Security (unclassified fundamental research that supports stockpile safety and nonproliferation programs). The LDRD program supports Office of Science strategic plans, including the 20-year Scientific Facilities Plan and the Office of Science Strategic Plan. The research also supports the strategic directions periodically under consideration and review by the

Horonobe Underground Research Laboratory project. Investigation report for the 2006 fiscal year

International Nuclear Information System (INIS)

Matsui, Hiroya; Nakayama, Masashi; Sanada, Hiroyuki

2008-05-01

The Horonobe Underground Research Laboratory is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2006 fiscal year (2006/2007), the second year of the Phase 2 investigations. The investigations, which are composed of 'Geoscientific research' and 'R and D on the geological disposal of high-level radioactive waste (HLW)', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2006 Fiscal Year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. JAEA proceeded with the project in, collaboration with experts from domestic and overseas research organisation. (author)

Horonobe Underground Research Laboratory project. Investigation report for the 2007 fiscal year

International Nuclear Information System (INIS)

Nakayama, Masashi; Sanada, Hiroyuki; Sugita, Yutaka

2008-09-01

The Horonobe Underground Research Laboratory Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2007 fiscal year (2007/2008), the 3rd year of the Phase 2 investigations. The investigations, which are composed of 'Geoscientific research' and 'R and D on the geological disposal of high-level radioactive waste (HLW)', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2007 Fiscal Year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. JAEA proceeded with the project in collaboration with experts from domestic and overseas research organisation. (author)

Horonobe Underground Research Laboratory project investigation report for the 2008 fiscal year

International Nuclear Information System (INIS)

Nakayama, Masashi; Sano, Michiaki; Sanada, Hiroyuki; Sugita, Yutaka

2009-11-01

The Horonobe Underground Research Laboratory Project is planned to extend over a period 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations' 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2008 fiscal year (2008/2009), the 4th year of the Phase 2 investigations. The investigations, which are composed of 'Geoscientific research' and 'R and D on geological disposal technology', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2008 Fiscal year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. For the sake of this, JAEA has proceeded with the project in collaboration with experts from domestic and overseas research organisations. (author)

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

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.

Research program on nuclear technology and nuclear safety - Synthesis report 2008

International Nuclear Information System (INIS)

Dreier, J.

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. Four main projects at the Paul Scherrer Institute's Laboratory for Reactor Physics and System Behaviour LRS are noted, and work done at the Laboratories for Thermohydraulics LTH, Nuclear Materials LNM, Final Depository Safety LES and Energy System Analyses LEA are discussed. The results obtained in thirteen areas of research in 2008 are discussed in some detail. 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 the PSI research and development projects referred to

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.)

[Perception of health and safety risks among workers pathology laboratories].

Science.gov (United States)

Alvarado-Cabrero, Isabel; Valencia-Cedillo, Raquel

2015-01-01

Health care workers are experiencing increasing numbers of occupational illnesses. Safety practices in anatomical pathology laboratories (APL) are crucial to prevent unnecessary exposures to both chemical and biological agents. The main goal of this study was to determine if pathologists perceptions and actual practice mirror regulatory guidelines. Current available recommendations for APL were reviewed and used to construct an online survey distributed to pathologists. The survey was completed by 121 participants. Eighty-seven (72 %) of respondents reported receiving inadequate safety training. Most pathologists (82 %) were not well-informed about biosafety practices. Sixty-three (52 %) participants felt that the risks of chemical and infectious disease exposures in the APL were low. Most respondents reported having a needle stick or cut (71 %). Eighty-six (71 %) of participants reported musculo skeletal problems. This study indicated that there is a need for improving training in anatomical pathology safety practices in Mexican laboratories as daily practices do not reflected current guidelines.

Safety requirements in the design of research reactors: A Canadian perspective

International Nuclear Information System (INIS)

Lee, A.G.; Langman, V.J.

2000-01-01

In Canada, the formal development of safety requirements for the design of research reactors in general began under an inter-organizational Small Reactor Criteria Committee. This committee developed safety and licensing criteria for use by several small reactor projects in their licensing discussions with the Atomic Energy Control Board. The small reactor projects or facilities represented included the MAPLE-X10 reactor, the proposed SES-10 heating reactor and its prototype, the SDR reactor at the Whiteshell Laboratories, the Korea Multipurpose Research Reactor (a.k.a., HANARO) in Korea, the SCORE project, and the McMaster University Nuclear Reactor. The top level set of criteria which form a safety philosophy and serve as a framework for more detailed developments was presented at an IAEA Conference in 1989. AECL continued this work to develop safety principles and design criteria for new small reactors. The first major application of this work has been to the design, safety analysis and licensing of the MAPLE 1 and 2 reactors for the MDS Nordion Medical Isotope Reactor Project. This paper provides an overview of the safety principles and design criteria. Examples of an implementation of these safety principles and design criteria are drawn from the work to design the MAPLE 1 and 2 reactors. (author)

National Chemistry Teacher Safety Survey

Science.gov (United States)

Plohocki, Barbra A.

This study evaluated the status of secondary school instructional chemistry laboratory safety using a survey instrument which focused on Teacher background Information, Laboratory Safety Equipment, Facility Safety, General Safety, and a Safety Content Knowledge Survey. A fifty question survey instrument based on recent research and questions developed by the researcher was mailed to 500 secondary school chemistry teachers who participated in the 1993 one-week Woodrow Wilson National Fellowship Foundation Chemistry Institute conducted at Princeton University, New Jersey. The data received from 303 respondents was analyzed by t tests and Analysis of Variance (ANOVA). The level of significance for the study was set at ~\\ performance on the Safety Content Knowledge Survey and secondary school chemistry teachers who have had undergraduate and/or graduate safety training and those who have not had undergraduate and/or graduate safety training. Secondary school chemistry teachers who attended school district sponsored safety inservices did not score higher on the Safety Content Knowledge Survey than teachers who did not attend school district sponsored safety inservice sessions. The type of school district (urban, suburban, or rural) had no significant correlation to the type of laboratory safety equipment found in the instructional chemistry laboratory. The certification area (chemistry or other type of certificate which may or may not include chemistry) of the secondary school teacher had no significant correlation to the type of laboratory equipment found in the instructional chemistry laboratory. Overall, this study indicated a majority of secondary school chemistry teachers were interested in attending safety workshops applicable to chemistry safety. Throughout this research project, many teachers indicated they were not adequately instructed on the collegiate level in science safety and had to rely on common sense and self-study in their future teaching careers.

Investigation of discharged aerosol nanoparticles during chemical precipitation and spray pyrolysis for developing safety measures in the nano research laboratory.

Science.gov (United States)

Kolesnikov, Еvgeny; Karunakaran, Gopalu; Godymchuk, Anna; Vera, Levina; Yudin, Andrey Grigorjevich; Gusev, Alexander; Kuznetsov, Denis

2017-05-01

Nowadays, the demands for the nanoparticles are increasing due to their tremendous applications in various fields. As a consequence, the discharge of nanoparticles into the atmosphere and environment is also increasing, posing a health threat and environmental damage in terms of pollution. Thus, an extensive research is essential to evaluate the discharge of these nanoparticles into the environment. Keeping this in mind, the present investigation aimed to analyze the discharge of aerosol nanoparticles that are synthesized in the laboratory via chemical precipitation and spray pyrolysis methods. The results indicated that the chemical precipitation method discharges a higher concentration of nanoparticles in the work site when compared to the spray pyrolysis method. The aerosol concentration also varied with the different steps involved during the synthesis of nanoparticles. The average particle's concentration in air for chemical precipitation and spray pyrolysis methods was around 1,037,476 and 883,421particles/cm 3 . In addition, the average total discharge of nanoparticles in the entire laboratory was also examined. A significant variation in the concentration of nanoparticles was noticed, during the processing of materials and the concentration of particles (14-723nm) exceeding the daily allowed concentration to about 70-170 times was observed over a period of 6 months. Thus, the results of the present study will be very useful in developing safety measures and would help in organizing the rules for people working in nanotechnology laboratories to minimize the hazardous effects. Copyright © 2017 Elsevier Inc. All rights reserved.

Safety culture assessment among laboratory personnel of a petrochemical company

Directory of Open Access Journals (Sweden)

M. Shekari

2014-05-01

.Conclusion: Strong and positive safety culture among laboratory personnel would prevent incidence of many occupational accidents. In another word, it would help organizations to facilitate access to higher standards.

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.

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.

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)

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

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)

Idaho national laboratory - a nuclear research center

International Nuclear Information System (INIS)

Zaidi Mohammed, K.

2006-01-01

Full text: The Idaho National Laboratory (INL) is committed to providing international nuclear leadership for the 21st Century, developing and demonstrating compelling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multi program national laboratories. INL runs three major programs - Nuclear, Security and Science. Nuclear programs covers the Advanced test reactor, Six Generation IV technology concepts selected for Rand D, targeting tumors - Boron Neutron Capture therapy. Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (INSE) under the Center for Advanced Energy Studies (CAES) and the Idaho State University (ISU). INSE will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer INSE is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'. (author)

Chemical research at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

Argonne National Laboratory is a research and development laboratory located 25 miles southwest of Chicago, Illinois. It has more than 200 programs in basic and applied sciences and an Industrial Technology Development Center to help move its technologies to the industrial sector. At Argonne, basic energy research is supported by applied research in diverse areas such as biology and biomedicine, energy conservation, fossil and nuclear fuels, environmental science, and parallel computer architectures. These capabilities translate into technological expertise in energy production and use, advanced materials and manufacturing processes, and waste minimization and environmental remediation, which can be shared with the industrial sector. The Laboratory`s technologies can be applied to help companies design products, substitute materials, devise innovative industrial processes, develop advanced quality control systems and instrumentation, and address environmental concerns. The latest techniques and facilities, including those involving modeling, simulation, and high-performance computing, are available to industry and academia. At Argonne, there are opportunities for industry to carry out cooperative research, license inventions, exchange technical personnel, use unique research facilities, and attend conferences and workshops. Technology transfer is one of the Laboratory`s major missions. High priority is given to strengthening U.S. technological competitiveness through research and development partnerships with industry that capitalize on Argonne`s expertise and facilities. The Laboratory is one of three DOE superconductivity technology centers, focusing on manufacturing technology for high-temperature superconducting wires, motors, bearings, and connecting leads. Argonne National Laboratory is operated by the University of Chicago for the U.S. Department of Energy.

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

Horonobe Underground Research Laboratory Project. Plans for surface-based investigations. Phase 1

International Nuclear Information System (INIS)

Goto, Junichi; Hama, Katsuhiro

2003-10-01

The Horonobe Underground Research Laboratory Project is an investigation project which is planned over 20 years. The investigations are conducted in the three phases: investigations from surface (Phase 1), investigations during construction of the underground facility (Phase 2) and investigations using the facility (Phase 3). Taking into account the results from 'H12: Project of Establish the Scientific and Technical Basis for HLW Disposal in Japan - Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan-' (JNC, 2000), research and development goals for the Horonobe URL project were re-defined as follows; a) Development of investigation technologies for the geological environment, b) Development of monitoring technologies for the geological environment, c) Study on the long-term stability of the geological environment, d) Development of the basis for engineering technologies in deep underground, e) Verification of technologies for engineered barriers, f) Development of detailed designing technologies of the repositories, and g) Improvement of safety assessment methodologies. Investigations for the goals a) to d) and e) to g) are conducted in the 'Geoscientific Research' and 'Research and Development on Geological Disposal', respectively. In Phase 1, a 'laboratory construction area' of a few kilometers square is selected based on the results from early stage investigations. Subsequent investigations are concentrated in the selected area and its periphery. Acquisition of data by surface-based investigations, modeling of the geological environment and predictions of changes in the geological environment caused by the construction of the underground facility, are conducted in a) Development of investigation technologies for the geological environment. Development and installation of monitoring equipments and data acquisition prior to the construction of the underground facility fall under b) Development of monitoring technologies

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)

Safety management at nuclear installations with research reactors. A comparison of five European installations

International Nuclear Information System (INIS)

Troen, H.; Lauridsen, B.

1997-11-01

Five European institutions with nuclear research reactors were visited to compare safety management among institutions similar to Risoe. Risoe is a National Laboratory and the main activities are research and development. In 1996 it was decided to look into safety management at Risoe again; the last revision was in 1972. The purpose was to make it more efficient and to emphasise, that the responsibility lies in the operating organisation. Information such as nuclear facilities at the institutions, the safety management organisation, emergency preparedness, and lists of radiation doses to the employees from the years 1995 and 1996 is given in the report. Also international requirements and recommendations are given in short. Furthermore the report contains some reflections on the development in safety management organisations in resent years and the conclusions drawn from the information gathered

Plutonium working group report on environmental, safety and health vulnerabilities associated with the department's plutonium storage. Volume II, Appendix B, Part 10: Sandia National Laboratories - New Mexico site assessment team report

International Nuclear Information System (INIS)

1994-09-01

On March 15, 1994, Secretary O'Leary directed the Office of Environment, Safety and Health to conduct an environment, safety and health (ES ampersand H) vulnerability study of plutonium at DOE sites. This report presents Sandia National Laboratories'/New Mexico (SNL/NM) response to that request. Sandia National Laboratories (SNL) is a multi-program laboratory operated for United States Department of Energy(DOE) by Martin Marietta Corporation. The primary mission of Sandia is research and development of nuclear weapons systems for concept to retirement. The laboratory also has extensive programs in nuclear reactor safety, nuclear safeguards, energy research, and microelectronics. The facilities addressed in the SNL/NM Site Assessment include the Hot Cell Facility (HCF), the Annular Core Research Reactor (ACRR), and dedicated on-site nuclear material storage facilities. Also included in the assessment were sealed radiation sources that contain plutonium

EFFECTIVENESS AND SAFETY OF STRATEGIES FOR OIL SPILL BIOREMEDIATION: POTENTIAL AND LIMITATION, LABORATORY TO FIELD (RESEARCH BRIEF)

Science.gov (United States)

Several important additional research efforts were identified during the development of test systems and protocols for assessing the effectiveness and environmental safety of oil spill commercial bioremediation agents (CBAs). Research that examined CBA efficacy issues included: (...

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

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

Occupational safety and health status of medical laboratories in Kajiado County, Kenya.

Science.gov (United States)

Tait, Fridah Ntinyari; Mburu, Charles; Gikunju, Joseph

2018-01-01

Despite the increasing interest in Occupational Safety and Health (OSH), seldom studies are available on OSH in medical laboratories from developing countries in general although a high number of injuries occur without proper documentation. It is estimated that every day 6,300 people die as a result of occupational accidents or work-related diseases resulting in over 2.3 million deaths per year. Medical laboratories handle a wide range of materials, potentially dangerous pathogenic agents and exposes health workers to numerous potential hazards. This study evaluated the status of OSH in medical laboratories in Kajiado County, Kenya. The objectives included establishment of biological, chemical and physical hazards; reviewing medical laboratories control measures; and enumerating factors hindering implementation of good practices in OSH. This was a cross-sectional descriptive study research design. Observation check lists, interview schedules and structured questionnaires were used. The study was carried out in 108 medical laboratories among 204 sampled respondents. Data was analysed using statistical package for social science (SPSS) 20 software. The commonest type of hazards in medical laboratories include; bacteria (80%) for Biological hazards; handling un-labelled and un-marked chemicals (38.2%) for chemical hazards; and laboratory equipment's dangerously placed (49.5%) for Physical hazards. According to Pearson's Product Moment Correlation analysis, not-wearing personal protective equipment's was statistically associated with exposure to hazards. Individual control measures were statistically significant at 0.01 significance level. Only 65.1% of the factors influencing implementation of OSH in medical laboratories were identified. Training has the highest contribution to good OSH practices.

Safety and Liability in the New Technology Laboratory

Science.gov (United States)

Haynie, W. J., III

2009-01-01

All laboratories, even modern high-tech ones, have some degree of hazard potential. It is the teacher's responsibility to make the lab as safe as possible and to do all that is reasonable and prudent to prevent accidents. The teacher's goal should be to insure the safety of every student. This goal is met best via well-planned instruction and…

Radioactive Solid Waste Storage and Disposal at Oak Ridge National Laboratory, Description and Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Bates, L.D.

2001-01-30

Oak Ridge National Laboratory (ORNL) is a principle Department of Energy (DOE) Research Institution operated by the Union Carbide Corporation - Nuclear Division (UCC-ND) under direction of the DOE Oak Ridge Operations Office (DOE-ORO). The Laboratory was established in east Tennessee, near what is now the city of Oak Ridge, in the mid 1940s as a part of the World War II effort to develop a nuclear weapon. Since its inception, disposal of radioactively contaminated materials, both solid and liquid, has been an integral part of Laboratory operations. The purpose of this document is to provide a detailed description of the ORNL Solid Waste Storage Areas, to describe the practice and procedure of their operation, and to address the health and safety impacts and concerns of that operation.

Laboratory for Large Data Research

Data.gov (United States)

Federal Laboratory Consortium — FUNCTION: The Laboratory for Large Data Research (LDR) addresses a critical need to rapidly prototype shared, unified access to large amounts of data across both the...

The National Fire Research Laboratory

Data.gov (United States)

Federal Laboratory Consortium — The National Fire Research Laboratory (NFRL) is adding a unique facility that will serve as a center of excellence for fireperformance of structures ranging in size...

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.)

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.)

Laboratory research at the clinical trials of Veterinary medicinal Products

OpenAIRE

ZHYLA M.I.

2011-01-01

The article analyses the importance of laboratory test methods, namely pathomorfological at conduct of clinical trials. The article focuses on complex laboratory diagnostics at determination of clinical condition of animals, safety and efficacy of tested medicinal product.

Theatre and laboratory workers' awareness of and safety practices ...

African Journals Online (AJOL)

Introduction: The consistent use of barrier protection among theatre workers is low in this region, so also is hepatitis B virus (HBV) vaccination. We assessed the level of awareness of HBV and hepatitis C virus (HCV), HBV vaccination and adoption of safety measures by theatre and laboratory workers. Methods: Structured ...

Research and development program for PWR safety at the CEA reactor thermal hydraulics laboratories

International Nuclear Information System (INIS)

Bernard, M.

1995-01-01

Since the start of the French electronuclear program, the three partners Fermate, EDF and Cea (DRN and IPSN) have devoted considerable effort to research and development for safety issues. In particular an important program on thermal hydraulics was initiated at the beginning of the seventies. It is illustrated by the development of the CATHARE thermalhydraulic safety code which includes physical models derived from a large experimental support program and the construction of the BETHSY integral facility which is aimed to assess both the CATHARE code and the physical relevance of the accident management procedures to be applied on reactors. The state of the art on this program is described with particular emphasis on the capabilities and the assessment of the last version of CATHARE and the lessons drawn from 50 BETHSY tests performed so far. The future plans for safety research cover the following strategy: - to solve the few problems identified on present computing tools and extend the assessment - to solve the few problems identified on present computing tools and extend the assessment - to perform safety studies on the basis of plant operation feedback - to contribute to treating the safety issues related to the future reactors and in particular the case of severe accidents which have to be taken into account from the design stage. The program on severe accidents is aimed to support the design studies performed by the industrial partners and to provide computing tools which model the various phases of severe accidents and will be validated on experiments performed with real and simulating materials. The main lines of the program are: - the development of the TOLBIAC 3D code for the thermal hydraulics of core melt pools, which will be validated against the Bali experiment presently under construction - the Sultan experiment, to study the capability of cooling by external flooding of the reactor vessel - the development of the MC-3D code for core melt

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.

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.

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

International Nuclear Information System (INIS)

Bair, W.J.

1984-02-01

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

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

Profile of central research and application laboratory of Aǧrı İbrahim Çeçen University

Science.gov (United States)

Türkoǧlu, Emir Alper; Kurt, Murat; Tabay, Dilruba

2016-04-01

Aǧrı İbrahim Çeçen University built a central research and application laboratory (CRAL) in the east of Turkey. The CRAL possesses 7 research and analysis laboratories, 12 experts and researchers, 8 standard rooms for guest researchers, a restaurant, a conference hall, a meeting room, a prey room and a computer laboratory. The CRAL aims certain collaborations between researchers, experts, clinicians and educators in the areas of biotechnology, bioimagining, food safety & quality, omic sciences such as genomics, proteomics and metallomics. It also intends to develop sustainable solutions in agriculture and animal husbandry, promote public health quality, collect scientific knowledge and keep it for future generations, contribute scientific awareness of all stratums of society, provide consulting for small initiatives and industries. It has been collaborated several scientific foundations since 2011.

Profile of central research and application laboratory of Ağrı İbrahim Çeçen University

International Nuclear Information System (INIS)

Türkoğlu, Emir Alper; Kurt, Murat; Tabay, Dilruba

2016-01-01

Ağrı İbrahim Çeçen University built a central research and application laboratory (CRAL) in the east of Turkey. The CRAL possesses 7 research and analysis laboratories, 12 experts and researchers, 8 standard rooms for guest researchers, a restaurant, a conference hall, a meeting room, a prey room and a computer laboratory. The CRAL aims certain collaborations between researchers, experts, clinicians and educators in the areas of biotechnology, bioimagining, food safety & quality, omic sciences such as genomics, proteomics and metallomics. It also intends to develop sustainable solutions in agriculture and animal husbandry, promote public health quality, collect scientific knowledge and keep it for future generations, contribute scientific awareness of all stratums of society, provide consulting for small initiatives and industries. It has been collaborated several scientific foundations since 2011.

Profile of central research and application laboratory of Ağrı İbrahim Çeçen University

Energy Technology Data Exchange (ETDEWEB)

Türkoğlu, Emir Alper, E-mail: eaturkoglu@yandex.com [Ağrı İbrahim Çeçen University, Faculty of Pharmacy, Department of Pharmaceutical Technology, Ağrı (Turkey); Ağrı İbrahim Çeçen University, Central Research and Application Laboratory, Ağrı (Turkey); Kurt, Murat, E-mail: muratkurt60@hotmail.com; Tabay, Dilruba, E-mail: dtabay@agri.edu.tr [Ağrı İbrahim Çeçen University, Central Research and Application Laboratory, Ağrı (Turkey)

2016-04-18

Ağrı İbrahim Çeçen University built a central research and application laboratory (CRAL) in the east of Turkey. The CRAL possesses 7 research and analysis laboratories, 12 experts and researchers, 8 standard rooms for guest researchers, a restaurant, a conference hall, a meeting room, a prey room and a computer laboratory. The CRAL aims certain collaborations between researchers, experts, clinicians and educators in the areas of biotechnology, bioimagining, food safety & quality, omic sciences such as genomics, proteomics and metallomics. It also intends to develop sustainable solutions in agriculture and animal husbandry, promote public health quality, collect scientific knowledge and keep it for future generations, contribute scientific awareness of all stratums of society, provide consulting for small initiatives and industries. It has been collaborated several scientific foundations since 2011.

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.)

Safety re-assessment of AECL test and research reactors

International Nuclear Information System (INIS)

Winfield, D.J.

1990-01-01

Atomic Energy of Canada Limited currently has four operating engineering test/research reactors of various sizes and ages; a new isotope-production reactor Maple-X10, under construction at Chalk River Nuclear Laboratories (CRNL), and a heating demonstration reactor, SDR, undergoing high-power commissioning at Whiteshell Nuclear Research Establishment (WNRE). The company is also performing design studies of small reactors for hot water and electricity production. The older reactors are ZED-2, PTR, NRX, and NRU; these range in age from 42 years (NRX) to 29 years (ZED-2). Since 1984, limited-scope safety re-assessments have been underway on three of these reactors (ZED-2, NRX AND NRU). ZED-2 and PTR are operated by the Reactor Physics Branch; all other reactors are operated by the respective site Reactor Operations Branches. For the older reactors the original safety reports produced were entirely deterministic in nature and based on the design-basis accident concept. The limited scope safety re-assessments for these older reactors, carried out over the past 5 years, have comprised both quantitative probabilistic safety-assessment techniques, such as event tree and fault analysis, and/or qualitative techniques, such as failure mode and effect analysis. The technique used for an individual assessment was dependent upon the specific scope required. This paper discusses the types of analyses carried out, specific insights/recommendations resulting from the analysis, and the plan for future analysis. In addition, during the last four years safety assessments have been carried out on the new isotope-, heat-, and electricity-producing reactors, as part of the safety design review, commissioning and licensing activities

2016 Fermilab Laboratory Directed Research & Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

Wester, W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

2016-05-25

Fermilab is executing Laboratory Directed Research and Development (LDRD) as outlined by order DOE O 413.2B in order to enhance and realize the mission of the laboratory in a manner that also supports the laboratory’s strategic objectives and the mission of the Department of Energy. LDRD funds enable scientific creativity, allow for exploration of “high risk, high payoff” research, and allow for the demonstration of new ideas, technical concepts, and devices. LDRD also has an objective of maintaining and enhancing the scientific and technical vitality of Fermilab. LDRD is able to fund employee-initiated proposals that address the current strategic objectives and better position Fermilab for future mission needs. The request for such funds is made in consideration of the investment needs, affordability, and directives from DOE and Congress. Review procedures of the proposals will insure that those proposals which most address the strategic goals of the DOE and the Laboratory or which best position Fermilab for the future will be recommended to the Laboratory Director who has responsibility for approval. The execution of each approved project will be the responsibility of the Principal Investigator, PI, who will follow existing Laboratory guidelines to ensure compliance with safety, environmental, and quality assurance practices. A Laboratory Director-appointed LDRD Coordinator will work with Committees, Laboratory Management, other Fermilab Staff, and the PI’s to oversee the implementation of policies and procedures of LDRD and provide the management and execution of this Annual Program Plan. FY16 represents third fiscal year in which LDRD has existed at Fermilab. The number of preliminary proposals (117) submitted in response to the LDRD Call for Proposals indicates very strong interest of the program within the Fermilab community. The first two Calls have resulted in thirteen active LDRD projects – and it is expected that between five and seven new

Laboratory Directed Research and Development Program FY2011

Energy Technology Data Exchange (ETDEWEB)

none, none

2012-04-27

Berkeley Lab's research and the Laboratory Directed Research and Development (LDRD) program support DOE's Strategic Themes that are codified in DOE's 2006 Strategic Plan (DOE/CF-0010), with a primary focus on Scientific Discovery and Innovation. For that strategic theme, the Fiscal Year (FY) 2011 LDRD projects support each one of the three goals through multiple strategies described in the plan. In addition, LDRD efforts support the four goals of Energy Security, the two goals of Environmental Responsibility, and Nuclear Security (unclassified fundamental research that supports stockpile safety and nonproliferation programs). Going forward in FY 2012, the LDRD program also supports the Goals codified in the new DOE Strategic Plan of May, 2011. The LDRD program also supports Office of Science strategic plans, including the 20-year Scientific Facilities Plan and the Office of Science Strategic Plan. The research also supports the strategic directions periodically under consideration and review by the Office of Science Program Offices, such as LDRD projects germane to new research facility concepts and new fundamental science directions. Brief summares of projects and accomplishments for the period for each division are included.

Laboratory Directed Research ampersand Development Program

International Nuclear Information System (INIS)

Ogeka, G.J.; Romano, A.J.

1993-12-01

At Brookhaven National Laboratory the Laboratory Directed Research and Development (LDRD) Program is a discretionary research and development tool critical in maintaining the scientific excellence and vitality of the laboratory. It is also a means to stimulate the scientific community, fostering new science and technology ideas, which is the major factor in achieving and maintaining staff excellence, and a means to address national needs, within the overall mission of the Department of Energy and Brookhaven National Laboratory. This report summarizes research which was funded by this program during fiscal year 1993. The research fell in a number of broad technical and scientific categories: new directions for energy technologies; global change; radiation therapies and imaging; genetic studies; new directions for the development and utilization of BNL facilities; miscellaneous projects. Two million dollars in funding supported 28 projects which were spread throughout all BNL scientific departments

Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

2013-01-01

The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

Establishment of a clean chemistry laboratory at JAERI. Clean laboratory for environmental analysis and research (CLEAR)

Energy Technology Data Exchange (ETDEWEB)

Hanzawa, Yukiko; Magara, Masaaki; Watanabe, Kazuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; and others

2003-02-01

The JAERI has established a facility with a cleanroom: the Clean Laboratory for Environmental Analysis and Research (CLEAR). This report is an overview of the design, construction and performance evaluation of the CLEAR in the initial stage of the laboratory operation in June 2001. The CLEAR is a facility to be used for analyses of ultra trace amounts of nuclear materials in environmental samples for the safeguards, for the CTBT verification and for researches on environmental sciences. One of the special features of the CLEAR is that it meets double requirements of a cleanroom and for handling of nuclear materials. As another feature of the CLEAR, much attention was paid to the construction materials of the cleanroom for trace analysis of metal elements using considerable amounts of corrosive acids. The air conditioning and purification system, specially designed experimental equipment to provide clean work surfaces, utilities and safety systems are also demonstrated. The potential contamination from the completed cleanroom atmosphere during the analytical procedure was evaluated. It can be concluded that the CLEAR has provided a suitable condition for reliable analysis of ultra trace amounts of nuclear materials and other heavy elements in environmental samples. (author)

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

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.)

Safety Precautions and Operating Procedures in an (A)BSL-4 Laboratory: 2. General Practices.

Science.gov (United States)

Mazur, Steven; Holbrook, Michael R; Burdette, Tracey; Joselyn, Nicole; Barr, Jason; Pusl, Daniela; Bollinger, Laura; Coe, Linda; Jahrling, Peter B; Lackemeyer, Matthew G; Wada, Jiro; Kuhn, Jens H; Janosko, Krisztina

2016-10-03

Work in a biosafety level 4 (BSL-4) containment laboratory requires time and great attention to detail. The same work that is done in a BSL-2 laboratory with non-high-consequence pathogens will take significantly longer in a BSL-4 setting. This increased time requirement is due to a multitude of factors that are aimed at protecting the researcher from laboratory-acquired infections, the work environment from potential contamination and the local community from possible release of high-consequence pathogens. Inside the laboratory, movement is restricted due to air hoses attached to the mandatory full-body safety suits. In addition, disinfection of every item that is removed from Class II biosafety cabinets (BSCs) is required. Laboratory specialists must be trained in the practices of the BSL-4 laboratory and must show high proficiency in the skills they are performing. The focus of this article is to outline proper procedures and techniques to ensure laboratory biosafety and experimental accuracy using a standard viral plaque assay as an example procedure. In particular, proper techniques to work safely in a BSL-4 environment when performing an experiment will be visually emphasized. These techniques include: setting up a Class II BSC for experiments, proper cleaning of the Class II BSC when finished working, waste management and safe disposal of waste generated inside a BSL-4 laboratory, and the removal of inactivated samples from inside a BSL-4 laboratory to the BSL-2 laboratory.

Errors in laboratory medicine: practical lessons to improve patient safety.

Science.gov (United States)

Howanitz, Peter J

2005-10-01

Patient safety is influenced by the frequency and seriousness of errors that occur in the health care system. Error rates in laboratory practices are collected routinely for a variety of performance measures in all clinical pathology laboratories in the United States, but a list of critical performance measures has not yet been recommended. The most extensive databases describing error rates in pathology were developed and are maintained by the College of American Pathologists (CAP). These databases include the CAP's Q-Probes and Q-Tracks programs, which provide information on error rates from more than 130 interlaboratory studies. To define critical performance measures in laboratory medicine, describe error rates of these measures, and provide suggestions to decrease these errors, thereby ultimately improving patient safety. A review of experiences from Q-Probes and Q-Tracks studies supplemented with other studies cited in the literature. Q-Probes studies are carried out as time-limited studies lasting 1 to 4 months and have been conducted since 1989. In contrast, Q-Tracks investigations are ongoing studies performed on a yearly basis and have been conducted only since 1998. Participants from institutions throughout the world simultaneously conducted these studies according to specified scientific designs. The CAP has collected and summarized data for participants about these performance measures, including the significance of errors, the magnitude of error rates, tactics for error reduction, and willingness to implement each of these performance measures. A list of recommended performance measures, the frequency of errors when these performance measures were studied, and suggestions to improve patient safety by reducing these errors. Error rates for preanalytic and postanalytic performance measures were higher than for analytic measures. Eight performance measures were identified, including customer satisfaction, test turnaround times, patient identification

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

Can TTIP Improve Laboratory Animal Welfare in Safety Testing and 3Rs?

Science.gov (United States)

Busquet, Francois; Zurlo, Joanne; Hartung, Thomas

2016-05-01

In the context of the current negotiations between the European Union (EU) and the United States under the Transatlantic Trade Investment Partnership (TTIP), there is the opportunity to look at both legislative frameworks to better pinpoint convergences, synergies, and gaps when it comes to use of laboratory animals for scientific purposes and bring together the best of both worlds. The objectives in this article are to indicate what are the current EU pieces of legislation that are relevant under TTIP regarding the uses of laboratory animals for scientific purposes under the regulations about cosmetics and chemicals, among others. The same approach will be taken to look at the relevant American legal frameworks, that is, the Food and Cosmetics Act and the Toxic Safety Control Act as well as its most recent reauthorization. In conclusion, the authors will identify future frameworks that can contribute to the harmonization of regulatory standards and further steps where TTIP negotiators should strengthen regulatory cooperation. © The Author 2016. Published by Oxford University Press on behalf of the Institute for Laboratory Animal Research. All rights reserved. For permissions, please email: journals.permissions@oup.com.

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.

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

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)

Bringing ayahuasca to the clinical research laboratory.

Science.gov (United States)

Riba, Jordi; Barbanoj, Manel J

2005-06-01

Since the winter of 1999, the authors and their research team have been conducting clinical studies involving the administration of ayahuasca to healthy volunteers. The rationale for conducting this kind of research is twofold. First, the growing interest of many individuals for traditional indigenous practices involving the ingestion of natural psychotropic drugs such as ayahuasca demands the systematic study of their pharmacological profiles in the target species, i.e., human beings. The complex nature of ayahuasca brews combining a large number of pharmacologically active compounds requires that research be carried out to establish the safety and overall pharmacological profile of these products. Second, the authors believe that the study of psychedelics in general calls for renewed attention. Although the molecular and electrophysiological level effects of these drugs are relatively well characterized, current knowledge of the mechanisms by which these compounds modify the higher order cognitive processes in the way they do is still incomplete, to say the least. The present article describes the development of the research effort carried out at the Autonomous University of Barcelona, commenting on several methodological aspects and reviewing the basic clinical findings. It also describes the research currently underway in our laboratory, and briefly comments on two new studies we plan to undertake in order to further our knowledge of the pharmacology of ayahuasca.

Fuel Combustion Laboratory | Transportation Research | NREL

Science.gov (United States)

Fuel Combustion Laboratory Fuel Combustion Laboratory NREL's Fuel Combustion Laboratory focuses on designs, using both today's technology and future advanced combustion concepts. This lab supports the combustion chamber platform for fuel ignition kinetics research, was acquired to expand the lab's

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

Network Science Research Laboratory (NSRL) Discrete Event Toolkit

Science.gov (United States)

2016-01-01

ARL-TR-7579 ● JAN 2016 US Army Research Laboratory Network Science Research Laboratory (NSRL) Discrete Event Toolkit by...Laboratory (NSRL) Discrete Event Toolkit by Theron Trout and Andrew J Toth Computational and Information Sciences Directorate, ARL...Research Laboratory (NSRL) Discrete Event Toolkit 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) Theron Trout

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

Energetic materials research and development activities at Sandia National Laboratories supported under DP-10 programs

Energy Technology Data Exchange (ETDEWEB)

Ratzel, A.C. III

1998-09-01

This report provides summary descriptions of Energetic Materials (EM) Research and Development activities performed at Sandia National Laboratories and funded through the Department of Energy DP-10 Program Office in FY97 and FY98. The work falls under three major focus areas: EM Chemistry, EM Characterization, and EM Phenomenological Model Development. The research supports the Sandia component mission and also Sandia's overall role as safety steward for the DOE Nuclear Weapons Complex.

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.)

[Clinical governance and patient safety culture in clinical laboratories in the Spanish National Health System].

Science.gov (United States)

Giménez-Marín, Á; Rivas-Ruiz, F

To conduct a situational analysis of patient safety culture in public laboratories in the Spanish National Health System and to determine the clinical governance variables that most strongly influence patient safety. A descriptive cross-sectional study was carried out, in which a Survey of Patient Safety in Clinical Laboratories was addressed to workers in 26 participating laboratories. In this survey, which consisted of 45 items grouped into 6 areas, scores were assigned on a scale from 0 to 100 (where 0 is the lowest perception of patient safety). Laboratory managers were asked specific questions about quality management systems and technology. The mean scores for the 26 participating hospitals were evaluated, and the following results observed: in 4of the 6areas, the mean score was higher than 70 points. In the third area (equipment and resources) and the fourth area (working conditions), the scores were lower than 60 points. Every hospital had a digital medical record system. This 100% level of provision was followed by that of an electronic request management system, which was implemented in 82.6% of the hospitals. The results obtained show that the culture of security is homogeneous and of high quality in health service laboratories, probably due to the steady improvement observed. However, in terms of clinical governance, there is still some way to go, as shown by the presence of weaknesses in crucial dimensions of safety culture, together with variable levels of implementation of fail-safe technologies and quality management systems. Copyright © 2017 SECA. Publicado por Elsevier España, S.L.U. All rights reserved.

Swedish Nuclear Power Inspectorate, Office of Reactor Safety. Research plans for the period 1997-1999

International Nuclear Information System (INIS)

1997-02-01

Office of Reactor Safety research is carried out within the following areas: Safety evaluation, Safety analysis, MTO, Materials and chemistry, Non-Destructive Testing, Strength of materials, Thermohydraulics, Nuclear fuel, Serious accidents and Process control. Research is carried out to fulfill SKIs overall goals in accordance with the directives from the Swedish government and parliament, in particular to be a driving force in safety related work when justified by operating experience, research results and technical progress, towards licensees as well as in international cooperation in safety; to promote the maintenance and development of competence in the safety related work at the SKI as well as the licensees and generally in the country, and as a specific role for the Office of Reactor Safety as designated in the internal routines to take initiative to encourage and carry out research into areas of importance for the Office as well as ensuring that research results are disseminated and used both within SKI and in the general work concerning nuclear safety. Research efforts within the Office of Reactor safety are carried out in the form of separate projects which form part of the priority work plans. Project managers, the necessary personnel resources and the budget for each year are included in the Annual Plan and the work is followed up in the same manner as other efforts. Research is performed in different ways, that can vary from laboratory studies to more consultative efforts, and be organised in many different ways such as examination projects, post-graduate studies, work sponsored at research institutes and companies in Sweden and abroad, collaboration in larger international projects, and participation in conferences which provide an important contribution to keeping SKI personnel informed within their specialist areas

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

Assessment of patient safety culture in clinical laboratories in the Spanish National Health System.

Science.gov (United States)

Giménez-Marín, Angeles; Rivas-Ruiz, Francisco; García-Raja, Ana M; Venta-Obaya, Rafael; Fusté-Ventosa, Margarita; Caballé-Martín, Inmaculada; Benítez-Estevez, Alfonso; Quinteiro-García, Ana I; Bedini, José Luis; León-Justel, Antonio; Torra-Puig, Montserrat

2015-01-01

There is increasing awareness of the importance of transforming organisational culture in order to raise safety standards. This paper describes the results obtained from an evaluation of patient safety culture in a sample of clinical laboratories in public hospitals in the Spanish National Health System. A descriptive cross-sectional study was conducted among health workers employed in the clinical laboratories of 27 public hospitals in 2012. The participants were recruited by the heads of service at each of the participating centers. Stratified analyses were performed to assess the mean score, standardized to a base of 100, of the six survey factors, together with the overall patient safety score. 740 completed questionnaires were received (88% of the 840 issued). The highest standardized scores were obtained in Area 1 (individual, social and cultural) with a mean value of 77 (95%CI: 76-78), and the lowest ones, in Area 3 (equipment and resources), with a mean value of 58 (95%CI: 57-59). In all areas, a greater perception of patient safety was reported by the heads of service than by other staff. We present the first multicentre study to evaluate the culture of clinical safety in public hospital laboratories in Spain. The results obtained evidence a culture in which high regard is paid to safety, probably due to the pattern of continuous quality improvement. Nevertheless, much remains to be done, as reflected by the weaknesses detected, which identify areas and strategies for improvement.

D and D of a plutonium research laboratory and related auxiliary systems

International Nuclear Information System (INIS)

Diaz Arocas, P.; Martinez Ortega, A.; Sama Colao, J.; Garcia Diaz, A.; Torre Rodriguez, J.; Diaz Diaz, J.L.; Argiles, E.; Garrido, C.

2010-01-01

CIEMAT, former Junta de Energia Nuclear (JEN) started nuclear research at the 60. decade, focussed on the development of pacific uses of Nuclear Energy. At that time, CIEMAT research and pilot plants developed involved the whole nuclear fuel cycle steps. It means from the uranium recovery to the spent fuel reprocessing. With this scope a plutonium research laboratory was constructed and operated from 1961 to the 90's focussed on chemistry of plutonium studies, separation processes and radiochemical analyses, in order to assist the working pilot plants at the Centre. Thereafter, as the result of the changes on the research objectives of CIEMAT, the plutonium laboratory suffered several modifications and finally it was safety stopped due to the obsolescence of its equipments and auxiliary systems. Present paper shows the D and D activities performed and techniques developed to avoid alpha emitter contamination. In every dismantling phase there were established the measures of operational radiological protection adapted to the radiological risk. Dosimetric controls realized during dismantlement showed that incorporation of radionuclides was not detected. Radiological final control was performed applying the derived levels of declassification to request the installation decommissioning. (authors)

Safety in Academic Chemistry Laboratories: Volume 1. Accident Prevention for College and University Students, 7th Edition.

Science.gov (United States)

American Chemical Society, Washington, DC.

This book contains volume 1 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Your Responsibility for Accident Prevention"; (2) "Guide to Chemical Hazards"; (3) "Recommended Laboratory Techniques"; and (4) "Safety Equipment and Emergency…

Green Building Research Laboratory

Energy Technology Data Exchange (ETDEWEB)

Sailor, David Jean [Portland State Univ., Portland, OR (United States)

2013-12-29

This project provided support to the Green Building Research Laboratory at Portland State University (PSU) so it could work with researchers and industry to solve technical problems for the benefit of the green building industry. It also helped to facilitate the development of PSU’s undergraduate and graduate-level training in building science across the curriculum.

Laboratory Technology Research: Abstracts of FY 1996 projects

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The Laboratory Technology Research (LTR) program supports high-risk, multidisciplinary research partnerships to investigate challenging scientific problems whose solutions have promising commercial potential. These partnerships capitalize on two great strengths of this country: the world-class basic research capability of the DOE Energy Research (ER) multi-program national laboratories and the unparalleled entrepreneurial spirit of American industry. Projects supported by the LTR program are conducted by the five ER multi-program laboratories: Argonne, Brookhaven, Lawrence Berkeley, Oak Ridge, and Pacific Northwest National Laboratories. These projects explore the applications of basic research advances relevant to Department of Energy`s (DOE) mission over a full range of scientific disciplines. The program presently emphasizes three critical areas of mission-related research: advanced materials, intelligent processing/manufacturing research, and sustainable environments.

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

The design of hot laboratories

International Nuclear Information System (INIS)

1976-01-01

The need for specialized laboratories to handle radioactive substances of high activity has increased greatly due to the expansion of the nuclear power industry and the widespread use of radioisotopes in scientific research and technology. Such laboratories, which are called hot laboratories, are specially designed and equipped to handle radioactive materials of high activity, including plutonium and transplutonium elements. The handling of plutonium and transplutonium elements presents special radiation-protection and safety problems because of their high specific activity and high radiotoxicity. Therefore, the planning, design, construction and operation of hot laboratories must meet the stringent safety, containment, ventilation, shielding, criticality control and fire-protection requirements. The IAEA has published two manuals in its Safety Series, one on the safety aspects of design and equipment of hot laboratories (SS No.30) and the other on the safe handling of plutonium (SS No.39). The purpose of the symposium in Otaniemi was to collect information on recent developments in the safety features of hot laboratories and to review the present state of knowledge. A number of new developments have taken place as the result of growing sophistication in the philosophy of radiation protection as given in the ICRP recommendations (Report No.22) and in the Agency's basic safety standards (No.9). The topics discussed were safety features of planning and design, air cleaning, transfer and transport systems, criticality control, fire protection, radiological protection, waste management, administrative arrangements and operating experience

The underground research laboratories

International Nuclear Information System (INIS)

1997-06-01

This educational booklet is a general presentation of the selected sites for the installation of underground research laboratories devoted to the feasibility studies of deep repositories for long-life radioactive wastes. It describes the different type of wastes and their management, the management of long life radioactive wastes, the site selection and the 4 sites retained, the preliminary research studies, and the other researches carried out in deep disposal facilities worldwide. (J.S.)

Risk assessment for safety laboratories in Politeknik Negeri Medan

Science.gov (United States)

Viyata Sundawa, Bakti; Hutajulu, Elferida; Sirait, Regina; Banurea, Waldemar; Indrayadi; Mulyadi, Sangap

2017-09-01

International Labour Organization (ILO) estimated 2.34 million people die each year because accidents and diseases in workplace. It also impact to economic losses in some countries. It need to do safety and healthy in working environment especially in laboratory. Identification of potential hazards and risks must be done in Telecommunication Laboratory Politeknik Negeri Medan. Therefore, this study was assessed 5 of potential hazards and risks in our laboratory by Likert Scale. This object was divided into 2 assessment namely likelihood of hazards and severity of consequences. Collecting data is taken from questionnaire who involved 100 students at random academic level. The result showed The highest score is chemical hazards 73.2% in likelihood of hazards and electrical hazards 85% in severity of consequences. This condition is classified as “high” state. Big attention must be given to “high” state because it can help us to determine mitigate action.

Evaluation of the effectiveness and safety of the thermo-treatment process to dispose of recombinant DNA waste from biological research laboratories.

Science.gov (United States)

Li, Meng-Nan; Zheng, Guang-Hong; Wang, Lei; Xiao, Wei; Fu, Xiao-Hua; Le, Yi-Quan; Ren, Da-Ming

2009-01-01

The discharge of recombinant DNA waste from biological laboratories into the eco-system may be one of the pathways resulting in horizontal gene transfer or "gene pollution". Heating at 100 degrees C for 5-10 min is a common method for treating recombinant DNA waste in biological research laboratories in China. In this study, we evaluated the effectiveness and the safety of the thermo-treatment method in the disposal of recombinant DNA waste. Quantitative PCR, plasmid transformation and electrophoresis technology were used to evaluate the decay/denaturation efficiency during the thermo-treatment process of recombinant plasmid, pET-28b. Results showed that prolonging thermo-treatment time could improve decay efficiency of the plasmid, and its decay half-life was 2.7-4.0 min during the thermo-treatment at 100 degrees C. However, after 30 min of thermo-treatment some transforming activity remained. Higher ionic strength could protect recombinant plasmid from decay during the treatment process. These results indicate that thermo-treatment at 100 degrees C cannot decay and inactivate pET-28b completely. In addition, preliminary results showed that thermo-treated recombinant plasmids were not degraded completely in a short period when they were discharged into an aquatic environment. This implies that when thermo-treated recombinant DNAs are discharged into the eco-system, they may have enough time to re-nature and transform, thus resulting in gene diffusion.

Evaluation of the effectiveness and safety of the thermo-treatment process to dispose of recombinant DNA waste from biological research laboratories

International Nuclear Information System (INIS)

Li Mengnan; Zheng Guanghong; Wang Lei; Xiao Wei; Fu Xiaohua; Le Yiquan; Ren Daming

2009-01-01

The discharge of recombinant DNA waste from biological laboratories into the eco-system may be one of the pathways resulting in horizontal gene transfer or 'gene pollution'. Heating at 100 deg. C for 5-10 min is a common method for treating recombinant DNA waste in biological research laboratories in China. In this study, we evaluated the effectiveness and the safety of the thermo-treatment method in the disposal of recombinant DNA waste. Quantitative PCR, plasmid transformation and electrophoresis technology were used to evaluate the decay/denaturation efficiency during the thermo-treatment process of recombinant plasmid, pET-28b. Results showed that prolonging thermo-treatment time could improve decay efficiency of the plasmid, and its decay half-life was 2.7-4.0 min during the thermo-treatment at 100 deg. C. However, after 30 min of thermo-treatment some transforming activity remained. Higher ionic strength could protect recombinant plasmid from decay during the treatment process. These results indicate that thermo-treatment at 100 deg. C cannot decay and inactivate pET-28b completely. In addition, preliminary results showed that thermo-treated recombinant plasmids were not degraded completely in a short period when they were discharged into an aquatic environment. This implies that when thermo-treated recombinant DNAs are discharged into the eco-system, they may have enough time to re-nature and transform, thus resulting in gene diffusion

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

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

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

Science | Argonne National Laboratory

Science.gov (United States)

Security Photon Sciences Physical Sciences & Engineering Energy Frontier Research Centers Scientific Publications Researchers Postdocs Exascale Computing Institute for Molecular Engineering at Argonne Work with Us About Safety News Careers Education Community Diversity Directory Argonne National Laboratory

Techniques in cancer research: a laboratory manual

International Nuclear Information System (INIS)

Deo, M.G.; Seshadri, R.; Mulherkar, R.; Mukhopadhyaya, R.

1995-01-01

Cancer Research Institute (CRI) works on all facets of cancer using the latest biomedical tools. For this purpose, it has established modern laboratories in different branches of cancer biology such as cell and molecular biology, biochemistry, immunology, chemical and viral oncogenesis, genetics of cancer including genetic engineering, tissue culture, cancer chemotherapy, neurooncology and comparative oncology. This manual describes the protocols used in these laboratories. There is also a chapter on handling and care of laboratory animals, an essential component of any modern cancer biology laboratory. It is hoped that the manual will be useful to biomedical laboratories, specially those interested in cancer research. refs., tabs., figs

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...

Testing laboratories, its function in ensuring industrial safety

International Nuclear Information System (INIS)

Sanchez Fernandez, M.

2015-01-01

This article discusses and justifies the development of industrial laboratories (testing and calibration) in Spain, since its embryo, its creation and development, to the present day. Likewise, presents its interrelation with other agents, as well as the legislative and technical framework is application along to the years. Within this development of the sector, highlights the period of the conformity assessment, and consequently its relationship with Industrial safety. Finally, describes the organizational situation of the sector both nationally and internationally. (Author)

Research programs at the Department of Energy National Laboratories. Volume 2: Laboratory matrix

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

For nearly fifty years, the US national laboratories, under the direction of the Department of Energy, have maintained a tradition of outstanding scientific research and innovative technological development. With the end of the Cold War, their roles have undergone profound changes. Although many of their original priorities remain--stewardship of the nation`s nuclear stockpile, for example--pressing budget constraints and new federal mandates have altered their focus. Promotion of energy efficiency, environmental restoration, human health, and technology partnerships with the goal of enhancing US economic and technological competitiveness are key new priorities. The multiprogram national laboratories offer unparalleled expertise in meeting the challenge of changing priorities. This volume aims to demonstrate each laboratory`s uniqueness in applying this expertise. It describes the laboratories` activities in eleven broad areas of research that most or all share in common. Each section of this volume is devoted to a single laboratory. Those included are: Argonne National Laboratory; Brookhaven National Laboratory; Idaho National Engineering Laboratory; Lawrence Berkeley Laboratory; Lawrence Livermore National Laboratory; Los Alamos National Laboratory; National Renewable Energy Laboratory; Oak Ridge National Laboratory; Pacific Northwest Laboratory; and Sandia National Laboratories. The information in this volume was provided by the multiprogram national laboratories and compiled at Lawrence Berkeley Laboratory.

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)

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.)

Advanced nuclear reactor safety design technology research in NPIC

International Nuclear Information System (INIS)

Yu, H.

2014-01-01

After the Fukushima accident happen, Nuclear Power Plants (NPPs) construction has been suspended in China for a time. Now the new regulatory rule has been proposed that the most advanced safety standard must be adopted for the new NPPs and practical elimination of large fission product release by design during the next five plans period. So the advanced reactor research is developing in China. NPIC is engaging on the ACP1000 and ACP100 (Small Module Reactor) design. The main design character will be introduced in this paper. The Passive Combined with Active (PCWA) design was adopted during the ACP1000 design to reduce the core damage frequency (CDF); the Cavity Injection System (CIS) is design to mitigation the consequence of the severe accident. Advance passive safety system was designed to ensure the long term residual heat removal during the Small Module Reactor (SMR). The SMR will be utilized to be the floating reactors, district heating reactor and so on. Besides, the Science and Technology on Reactor System Design Technology Laboratory (LRSDT) also engaged on the fundamental thermal-hydraulic characteristic research in support of the system validation. (author)

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)

A survey of costs incurred in U.K. X-ray diffraction research laboratories as a consequence of proposed regulations for radiological safety

International Nuclear Information System (INIS)

Blow, D.M.

1981-01-01

A small survey of British X-ray diffraction laboratories was undertaken, with the aim of discovering the effects of the Health and Safety at Work Act (1974) and the draft regulations on radiological protection and ionising radiations (1978) on the practice of X-ray crystallography. The responses lead to the conclusion that the average cost incurred in bringing X-ray diffraction equipment to a safety standard compatible with the draft regulations (as judged by the respondents) will exceed Pound2,000 per X-ray generator. The safety costs will represent an overhead charge of at least 15-18% on the purchase of an X-ray generator, requiring additional capital outlay of over Pound5m to maintain the current level of X-ray diffraction activity in the U.K. There seems to be no evidence of a high accident rate with diffraction equipment, and the cost of the safety precautions bears no relation to the risks involved. (author)

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

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.)

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.)

Cerebrospinal fluid protein and glucose examinations and tuberculosis:
Will laboratory safety regulations force a change of practice?

Science.gov (United States)

Tormey, William P; O'Hagan, Christopher

2015-01-01

Cerebrospinal fluid (CSF) protein and glucose examinations are usually performed in chemical pathology departments on autoanalysers. Tuberculosis (TB) is a group 3 biological agent under Directive 2000/54/EC of the European Parliament but in the biochemistry laboratory, no extra precautions are taken in its analysis in possible TB cases. The issue of laboratory practice and safety in the biochemical analyses of CSF specimens, when tuberculosis infection is in question is addressed in the context of ambiguity in the implementation of current national and international health and safety regulations. Additional protective measures for laboratory staff during the analysis of CSF TB samples should force a change in current laboratory practice and become a regulatory issue under ISO 15189. Annual Mantoux skin test or an interferon-γ release assay for TB should be mandatory for relevant staff. This manuscript addresses the issue of biochemistry laboratory practice and safety in the biochemical analyses of CSF specimens when tuberculosis infection is in question in the context of the ambiguity of statutory health and safety regulations.

Idaho National Laboratory Integrated Safety Management System 2011 Effectiveness Review and Declaration Report

Energy Technology Data Exchange (ETDEWEB)

Farren Hunt

2011-12-01

Idaho National Laboratory (INL) performed an annual Integrated Safety Management System (ISMS) effectiveness review per 48 Code of Federal Regulations (CFR) 970.5223-1, 'Integration of Environment, Safety and Health into Work Planning and Execution.' The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and helped identify target areas for focused improvements and assessments for fiscal year (FY) 2012. The information presented in this review of FY 2011 shows that the INL has performed many corrective actions and improvement activities, which are starting to show some of the desired results. These corrective actions and improvement activities will continue to help change culture that will lead to better implementation of defined programs, resulting in moving the Laboratory's performance from the categorization of 'Needs Improvement' to the desired results of 'Effective Performance.'

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)

Safety and protection problems in the management of a plant with cyclotron, radiopharmacy laboratory and PET/CT equipment

Energy Technology Data Exchange (ETDEWEB)

Russo, A.; Speranza, A.; Panico, M. [University Federico-2, National Research Council - Institute of Biostructures and Bioimaging and Dept. of Bio-morphological and Functional Sciences, Napoli (Italy); Delia, R. [University La Sapienza - sez. Rieti, Faculty of Medicine, Rome (Italy); Casale, M. [University Federico-2, Dept. of Physics - Health Physics School, Napoli (Italy); Salvatore, M. [University Federico-2 and National Research Council - Institute of Biostructures and Bioimaging, Dept. of Bio-morphological and Functional Sciences, Napoli (Italy)

2006-07-01

The importance of Positron Emission Tomography (PET) is spreading and increasing in many clinical diagnostic fields, as well as the oncology, the cardiology, the neurology and so on. A strong input to the diffusion of this imaging technique from the research field to clinical one has been given either by the development of knowledge about PET or the modern technologies, which allow to set up at very suitable prices and in very little volumes, like in an hospital site, complete systems, which consist of: Cyclotron; Radiopharmacy Laboratory; one or more either PET or PET/CT. Such set-up arrangement allows to carry out highly innovative diagnostic examinations with a remarkable achievement of diagnostic quality and large number of daily examinations. In this paper the authors show the achieved know-how with respect to radioprotection for the set-up and running management of two systems such as PET/CT tomography unit, cyclotron and radiopharmacy laboratory, installed one in the Imaging Diagnostic Department of the Hospital of Naples University and used only for medical and research purposes, and the other one in A.C.O.M. (Advanced Center of Oncology in Macerata), used for commercial and research purposes. The following safety problems have been considered: the facility lay-out; the optimisation of the paths either for the operator, or the patients and the radiotracers; the guide lines for the protection and the safety of the patients, operators and general population, in relation to the utilization and the management of either the more common radiotracers (18 F and 11 C) or those in research progress, for example 64 Cu and 124 I; the protocol set up for the image quality control in relation to the patient protection and safety. The above problems have also been considered, taking into account the Italian regulation and the International Recommendations. (authors)

Safety and protection problems in the management of a plant with cyclotron, radiopharmacy laboratory and PET/CT equipment

International Nuclear Information System (INIS)

Russo, A.; Speranza, A.; Panico, M.; Delia, R.; Casale, M.; Salvatore, M.

2006-01-01

The importance of Positron Emission Tomography (PET) is spreading and increasing in many clinical diagnostic fields, as well as the oncology, the cardiology, the neurology and so on. A strong input to the diffusion of this imaging technique from the research field to clinical one has been given either by the development of knowledge about PET or the modern technologies, which allow to set up at very suitable prices and in very little volumes, like in an hospital site, complete systems, which consist of: Cyclotron; Radiopharmacy Laboratory; one or more either PET or PET/CT. Such set-up arrangement allows to carry out highly innovative diagnostic examinations with a remarkable achievement of diagnostic quality and large number of daily examinations. In this paper the authors show the achieved know-how with respect to radioprotection for the set-up and running management of two systems such as PET/CT tomography unit, cyclotron and radiopharmacy laboratory, installed one in the Imaging Diagnostic Department of the Hospital of Naples University and used only for medical and research purposes, and the other one in A.C.O.M. (Advanced Center of Oncology in Macerata), used for commercial and research purposes. The following safety problems have been considered: the facility lay-out; the optimisation of the paths either for the operator, or the patients and the radiotracers; the guide lines for the protection and the safety of the patients, operators and general population, in relation to the utilization and the management of either the more common radiotracers (18 F and 11 C) or those in research progress, for example 64 Cu and 124 I; the protocol set up for the image quality control in relation to the patient protection and safety. The above problems have also been considered, taking into account the Italian regulation and the International Recommendations. (authors)

Summary of nuclear plant aging research at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Eissenberg, D.M.

1991-01-01

Oak Ridge National Laboratory (ORNL) has been a major contributor to the Nuclear Regulatory Commission (NRC) Nuclear Plant Aging Research Program since its inception. The research at ORNL has consisted primarily of the preparation of comprehensive aging assessments and other studies of safety related and other components and systems. The components and systems have been identified and prioritized based on risk considerations, as well as by operating experience. In each case, ORNL has been preparing a Phase 1 assessment which summarizes design features, operating conditions, and stressors which lead to degradation and failure; identified parameters which could be used to detect, trend and differentiate the degradations; and proposed potential inspection, surveillance, and monitoring methods which could be applied to the parameters. Where appropriate, Phase 2 assessments have been prepared, which verify and recommend inspection, surveillance and monitoring methods based on vendor information, laboratory and field tests, and in-situ inspections and tests. Finally, Phase 3 assessments are prepared which provide recommendations regarding implementing the inspection, surveillance and monitoring methods, and provide recommendations regarding criteria to be applied. Other activities include providing assistance to NRC/Nuclear Regulatory Research and regional offices as requested, and participation in ASME and IEEE codes and standards

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

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

The Swedish Research Councils' Laboratory progress report for 1975

International Nuclear Information System (INIS)

Rudstam, G.

1976-01-01

The Swedish Research Councils' Laboratory herewith presents its progress report for 1975. The report summarizes the current projects carried out by the research groups working at the laboratory. The very efficient assistance of the staff of the laboratory is greatfully acknowledged. The laboratory has been financially supported by the Atomic Research Council, the Medical Research Council, the Natural Science Research Council, and the Board of Technical Development. Valuable support in various ways has also been given by the Atomic Energy Company (AB Atomenergi). (author)

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

An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

Energy Technology Data Exchange (ETDEWEB)

Calderoni, P., E-mail: Pattrick.Calderoni@inl.gov [Fusion Safety Program, Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-7113 (United States); Sharpe, J.; Shimada, M.; Denny, B.; Pawelko, B.; Schuetz, S.; Longhurst, G. [Fusion Safety Program, Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-7113 (United States); Hatano, Y.; Hara, M. [Hydrogen Isotope Research Center, University of Toyama, Gofuku 3190, Toyama 930-8555 (Japan); Oya, Y. [Radioscience Research Laboratory, Faculty of Science, Shizuoka University, 836 Ohya, Suruga-ku, Shizuoka 422-8529 (Japan); Otsuka, T.; Katayama, K. [Interdisciplinary Graduate School of Engineering Sciences, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581 (Japan); Konishi, S.; Noborio, K.; Yamamoto, Y. [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)

2011-10-01

The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

International Nuclear Information System (INIS)

Calderoni, P.; Sharpe, J.; Shimada, M.; Denny, B.; Pawelko, B.; Schuetz, S.; Longhurst, G.; Hatano, Y.; Hara, M.; Oya, Y.; Otsuka, T.; Katayama, K.; Konishi, S.; Noborio, K.; Yamamoto, Y.

2011-01-01

The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

Quality Indicators in Laboratory Medicine: the status of the progress of IFCC Working Group "Laboratory Errors and Patient Safety" project.

Science.gov (United States)

Sciacovelli, Laura; Lippi, Giuseppe; Sumarac, Zorica; West, Jamie; Garcia Del Pino Castro, Isabel; Furtado Vieira, Keila; Ivanov, Agnes; Plebani, Mario

2017-03-01

The knowledge of error rates is essential in all clinical laboratories as it enables them to accurately identify their risk level, and compare it with those of other laboratories in order to evaluate their performance in relation to the State-of-the-Art (i.e. benchmarking) and define priorities for improvement actions. Although no activity is risk free, it is widely accepted that the risk of error is minimized by the use of Quality Indicators (QIs) managed as a part of laboratory improvement strategy and proven to be suitable monitoring and improvement tools. The purpose of QIs is to keep the error risk at a level that minimizes the likelihood of patients. However, identifying a suitable State-of-the-Art is challenging, because it calls for the knowledge of error rates measured in a variety of laboratories throughout world that differ in their organization and management, context, and the population they serve. Moreover, it also depends on the choice of the events to keep under control and the individual procedure for measurement. Although many laboratory professionals believe that the systemic use of QIs in Laboratory Medicine may be effective in decreasing errors occurring throughout the total testing process (TTP), to improve patient safety as well as to satisfy the requirements of International Standard ISO 15189, they find it difficult to maintain standardized and systematic data collection, and to promote continued high level of interest, commitment and dedication in the entire staff. Although many laboratories worldwide express a willingness to participate to the Model of QIs (MQI) project of IFCC Working Group "Laboratory Errors and Patient Safety", few systematically enter/record their own results and/or use a number of QIs designed to cover all phases of the TTP. Many laboratories justify their inadequate participation in data collection of QIs by claiming that the number of QIs included in the MQI is excessive. However, an analysis of results suggests

Quality Indicators in Laboratory Medicine: from theory to practice. Preliminary data from the IFCC Working Group Project "Laboratory Errors and Patient Safety".

Science.gov (United States)

Sciacovelli, Laura; O'Kane, Maurice; Skaik, Younis Abdelwahab; Caciagli, Patrizio; Pellegrini, Cristina; Da Rin, Giorgio; Ivanov, Agnes; Ghys, Timothy; Plebani, Mario

2011-05-01

The adoption of Quality Indicators (QIs) has prompted the development of tools to measure and evaluate the quality and effectiveness of laboratory testing, first in the hospital setting and subsequently in ambulatory and other care settings. While Laboratory Medicine has an important role in the delivery of high-quality care, no consensus exists as yet on the use of QIs focussing on all steps of the laboratory total testing process (TTP), and further research in this area is required. In order to reduce errors in laboratory testing, the IFCC Working Group on "Laboratory Errors and Patient Safety" (WG-LEPS) developed a series of Quality Indicators, specifically designed for clinical laboratories. In the first phase of the project, specific QIs for key processes of the TTP were identified, including all the pre-, intra- and post-analytic steps. The overall aim of the project is to create a common reporting system for clinical laboratories based on standardized data collection, and to define state-of-the-art and Quality Specifications (QSs) for each QI independent of: a) the size of organization and type of activities; b) the complexity of processes undertaken; and c) different degree of knowledge and ability of the staff. The aim of the present paper is to report the results collected from participating laboratories from February 2008 to December 2009 and to identify preliminary QSs. The results demonstrate that a Model of Quality Indicators managed as an External Quality Assurance Program can serve as a tool to monitor and control the pre-, intra- and post-analytical activities. It might also allow clinical laboratories to identify risks that lead to errors resulting in patient harm: identification and design of practices that eliminate medical errors; the sharing of information and education of clinical and laboratory teams on practices that reduce or prevent errors; the monitoring and evaluation of improvement activities.

Savannah River Ecology Laboratory. Annual technical progress report of ecological research, period ending July 31, 1994

Energy Technology Data Exchange (ETDEWEB)

1994-07-31

The Savannah River Ecology Laboratory (SREL) is a research unit of the University of Georgia (UGA) that is managed in conjunction with the University`s Institute of Ecology. The laboratory`s overall mission is to acquire and communicate knowledge of ecological processes and principles. SREL conducts basic and applied ecological research, as well as education and outreach programs, under an M&O contract with the US Department of Energy at the Savannah River Site. Significant accomplishments were made during the year ending July 31, 1994 in the areas of research, education and service. Reviewed in this document are research projects in the following areas: Environmental Operations Support (impacted wetlands, streams, trace organics, radioecology, database synthesis, wild life studies, zooplankton, safety and quality assurance); wood stork foraging and breeding ecology; defence waste processing facility; environmental risk assessment (endangered species, fish, ash basin studies); ecosystem alteration by chemical pollutants; wetlands systems; biodiversity on the SRS; Environmental toxicology; environmental outreach and education; Par Pond drawdown studies in wildlife and fish and metals; theoretical ecology; DOE-SR National Environmental Research Park; wildlife studies. Summaries of educational programs and publications are also give.

Argonne Research Library | Argonne National Laboratory

Science.gov (United States)

Argonne Argonne Research Library The Argonne Research Library supports the scientific and technical research needs of Argonne National Laboratory employees. Our library catalog is available via the Research questions or concerns, please contact us at librarians@anl.gov. Contact the Library Argonne Research Library

Idaho National Laboratory Integrated Safety Management System FY 2016 Effectiveness Review and Declaration Report

International Nuclear Information System (INIS)

Hunt, Farren J.

2016-01-01

Idaho National Laboratory's (INL's) Integrated Safety Management System (ISMS) effectiveness review of fiscal year (FY) 2016 shows that INL has integrated management programs and safety elements throughout the oversight and operational activities performed at INL. The significant maturity of Contractor Assurance System (CAS) processes, as demonstrated across INL's management systems and periodic reporting through the Management Review Meeting process, over the past two years has provided INL with current real-time understanding and knowledge pertaining to the health of the institution. INL's sustained excellence of the Integrated Safety and effective implementation of the Worker Safety and Health Program is also evidenced by other external validations and key indicators. In particular, external validations include VPP, ISO 14001, DOELAP accreditation, and key Laboratory level indicators such as ORPS (number, event frequency and severity); injury/illness indicators such as Days Away, Restricted and Transfer (DART) case rate, back & shoulder metric and open reporting indicators, demonstrate a continuous positive trend and therefore improved operational performance over the last few years. These indicators are also reflective of the Laboratory's overall organizational and safety culture improvement. Notably, there has also been a step change in ESH&Q Leadership actions that have been recognized both locally and complex-wide. Notwithstanding, Laboratory management continues to monitor and take action on lower level negative trends in numerous areas including: Conduct of Operations, Work Control, Work Site Analysis, Risk Assessment, LO/TO, Fire Protection, and Life Safety Systems, to mention a few. While the number of severe injury cases has decreased, as evidenced by the reduction in the DART case rate, the two hand injuries and the fire truck/ambulance accident were of particular concern. Aggressive actions continue in order to understand the causes and define actions

Physics Research at the Naval Research Laboratory

Science.gov (United States)

Coffey, Timothy

2001-03-01

The United States Naval Research Laboratory conducts a broad program of research into the physical properties of matter. Studies range from low temperature physics, such as that associated with superconducting systems to high temperature systems such as laser produced or astrophysical plasmas. Substantial studies are underway on surface science and nanoscience. Studies are underway on the electronic and optical properties of materials. Studies of the physical properties of the ocean and the earth’s atmosphere are of considerable importance. Studies of the earth’s sun particularly as it effects the earth’s ionosphere and magnetosphere are underway. The entire program involves a balance of laboratory experiments, field experiments and supporting theoretical and computational studies. This talk will address NRL’s funding of physics, its employment of physicists and will illustrate the nature of NRL’s physics program with several examples of recent accomplishments.

Laboratory directed research and development program, FY 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-02-01

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) Laboratory Directed Research and Development Program FY 1996 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the projects supported and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development (LDRD) program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The Berkeley Lab LDRD program is a critical tool for directing the Laboratory`s forefront scientific research capabilities toward vital, excellent, and emerging scientific challenges. The program provides the resources for Berkeley Lab scientists to make rapid and significant contributions to critical national science and technology problems. The LDRD program also advances the Laboratory`s core competencies, foundations, and scientific capability, and permits exploration of exciting new opportunities. Areas eligible for support include: (1) Work in forefront areas of science and technology that enrich Laboratory research and development capability; (2) Advanced study of new hypotheses, new experiments, and innovative approaches to develop new concepts or knowledge; (3) Experiments directed toward proof of principle for initial hypothesis testing or verification; and (4) Conception and preliminary technical analysis to explore possible instrumentation, experimental facilities, or new devices.

Sandia National Laboratories:

Science.gov (United States)

Environmental Management System Pollution Prevention History 60 impacts Diversity Locations Facts & Figures Programs Nuclear Weapons About Nuclear Weapons Safety & Security Weapons Science & Technology Robotics R&D 100 Awards Laboratory Directed Research & Development Technology Deployment Centers

A Research-Based Laboratory Course Designed to Strengthen the Research-Teaching Nexus

Science.gov (United States)

Parra, Karlett J.; Osgood, Marcy P.; Pappas, Donald L., Jr.

2010-01-01

We describe a 10-week laboratory course of guided research experiments thematically linked by topic, which had an ultimate goal of strengthening the undergraduate research-teaching nexus. This undergraduate laboratory course is a direct extension of faculty research interests. From DNA isolation, characterization, and mutagenesis, to protein…

Safety climate in university and college laboratories: impact of organizational and individual factors.

Science.gov (United States)

Wu, Tsung-Chih; Liu, Chi-Wei; Lu, Mu-Chen

2007-01-01

Universities and colleges serve to be institutions of education excellence; however, problems in the areas of occupational safety may undermine such goals. Occupational safety must be the concern of every employee in the organization, regardless of job position. Safety climate surveys have been suggested as important tools for measuring the effectiveness and improvement direction of safety programs. Thus, this study aims to investigate the influence of organizational and individual factors on safety climate in university and college laboratories. Employees at 100 universities and colleges in Taiwan were mailed a self-administered questionnaire survey; the response rate was 78%. Multivariate analysis of variance revealed that organizational category of ownership, the presence of a safety manager and safety committee, gender, age, title, accident experience, and safety training significantly affected the climate. Among them, accident experience and safety training affected the climate with practical significance. The authors recommend that managers should address important factors affecting safety issues and then create a positive climate by enforcing continuous improvements.

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...

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...

Promoting Good Clinical Laboratory Practices and Laboratory Accreditation to Support Clinical Trials in Sub-Saharan Africa

Science.gov (United States)

Shott, Joseph P.; Saye, Renion; Diakité, Moussa L.; Sanogo, Sintry; Dembele, Moussa B.; Keita, Sekouba; Nagel, Mary C.; Ellis, Ruth D.; Aebig, Joan A.; Diallo, Dapa A.; Doumbo, Ogobara K.

2012-01-01

Laboratory capacity in the developing world frequently lacks quality management systems (QMS) such as good clinical laboratory practices, proper safety precautions, and adequate facilities; impacting the ability to conduct biomedical research where it is needed most. As the regulatory climate changes globally, higher quality laboratory support is needed to protect study volunteers and to accurately assess biological parameters. The University of Bamako and its partners have undertaken a comprehensive QMS plan to improve quality and productivity using the Clinical and Laboratory Standards Institute standards and guidelines. The clinical laboratory passed the College of American Pathologists inspection in April 2010, and received full accreditation in June 2010. Our efforts to implement high-quality standards have been valuable for evaluating safety and immunogenicity of malaria vaccine candidates in Mali. Other disease-specific research groups in resource-limited settings may benefit by incorporating similar training initiatives, QMS methods, and continual improvement practices to ensure best practices. PMID:22492138

Laboratory technology research - abstracts of FY 1997 projects

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

The Laboratory Technology Research (LTR) program supports high-risk, multidisciplinary research partnerships to investigate challenging scientific problems whose solutions have promising commercial potential. These partnerships capitalize on two great strengths of this country: the world-class basic research capability of the DOE Energy Research (ER) multi-program national laboratories and the unparalleled entrepreneurial spirit of American industry. A distinguishing feature of the ER multi-program national laboratories is their ability to integrate broad areas of science and engineering in support of national research and development goals. The LTR program leverages this strength for the Nation`s benefit by fostering partnerships with US industry. The partners jointly bring technology research to a point where industry or the Department`s technology development programs can pursue final development and commercialization. Projects supported by the LTR program are conducted by the five ER multi-program laboratories. These projects explore the applications of basic research advances relevant to DOE`s mission over a full range of scientific disciplines. The program presently emphasizes three critical areas of mission-related research: advanced materials; intelligent processing/manufacturing research; and sustainable environments.

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.)

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory

Energy Technology Data Exchange (ETDEWEB)

J. D. Bess; J. B. Briggs; A. S. Garcia

2011-09-01

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory

International Nuclear Information System (INIS)

Bess, J.D.; Briggs, J.B.; Garcia, A.S.

2011-01-01

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

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.)

Laboratory Directed Research and Development Program

Energy Technology Data Exchange (ETDEWEB)

Ogeka, G.J.

1991-12-01

Today, new ideas and opportunities, fostering the advancement of technology, are occurring at an ever-increasing rate. It, therefore, seems appropriate that a vehicle be available which fosters the development of these new ideas and technologies, promotes the early exploration and exploitation of creative and innovative concepts, and which develops new fundable'' R D projects and programs. At Brookhaven National Laboratory (BNL), one such method is through its Laboratory Directed Research and Development (LDRD) Program. This discretionary research and development tool is critical in maintaining the scientific excellence and vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community, fostering new science and technology ideas, which is the major factor achieving and maintaining staff excellence, and a means to address national needs, with the overall mission of the Department of Energy (DOE) and the Brookhaven National Laboratory. The Project Summaries with their accomplishments described in this report reflect the above. Aside from leading to new fundable or promising programs and producing especially noteworthy research, they have resulted in numerous publications in various professional and scientific journals, and presentations at meetings and forums.

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)

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.

Strengthening LLNL Missions through Laboratory Directed Research and Development in High Performance Computing

Energy Technology Data Exchange (ETDEWEB)

Willis, D. K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-12-01

High performance computing (HPC) has been a defining strength of Lawrence Livermore National Laboratory (LLNL) since its founding. Livermore scientists have designed and used some of the world’s most powerful computers to drive breakthroughs in nearly every mission area. Today, the Laboratory is recognized as a world leader in the application of HPC to complex science, technology, and engineering challenges. Most importantly, HPC has been integral to the National Nuclear Security Administration’s (NNSA’s) Stockpile Stewardship Program—designed to ensure the safety, security, and reliability of our nuclear deterrent without nuclear testing. A critical factor behind Lawrence Livermore’s preeminence in HPC is the ongoing investments made by the Laboratory Directed Research and Development (LDRD) Program in cutting-edge concepts to enable efficient utilization of these powerful machines. Congress established the LDRD Program in 1991 to maintain the technical vitality of the Department of Energy (DOE) national laboratories. Since then, LDRD has been, and continues to be, an essential tool for exploring anticipated needs that lie beyond the planning horizon of our programs and for attracting the next generation of talented visionaries. Through LDRD, Livermore researchers can examine future challenges, propose and explore innovative solutions, and deliver creative approaches to support our missions. The present scientific and technical strengths of the Laboratory are, in large part, a product of past LDRD investments in HPC. Here, we provide seven examples of LDRD projects from the past decade that have played a critical role in building LLNL’s HPC, computer science, mathematics, and data science research capabilities, and describe how they have impacted LLNL’s mission.

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)

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)

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

Laboratory Animal Technician | Center for Cancer Research

Science.gov (United States)

PROGRAM DESCRIPTION The Laboratory Animal Sciences Program (LASP) provides exceptional quality animal care and technical support services for animal research performed at the National Cancer Institute at the Frederick National Laboratory for Cancer Research. LASP executes this mission by providing a broad spectrum of state-of-the-art technologies and services that are focused

Knowledge, attitude, and practice (KAP) of 'teaching laboratory' technicians towards laboratory safety and waste management: a pilot interventional study.

Science.gov (United States)

El-Gilany, A-H; El-Shaer, S; Khashaba, E; El-Dakroory, S A; Omar, N

2017-06-01

A quasi-experimental study was performed on 20 technicians working in the Faculty of Medicine, Mansoura University, Egypt. The knowledge, attitude, and practice (KAP) of laboratory technicians was measured before and two months after enrolling them in an intervention programme about laboratory best practice procedures. The programme addressed laboratory safety and medical waste management. The assessment was performed using a validated Arabic self-administered questionnaire. Pre- and post-intervention scores were compared using non-parametric tests. There are significant increases in the scores of KAP after implementation of the training programme. Copyright © 2017 The Healthcare Infection Society. Published by Elsevier Ltd. All rights reserved.

Patient safety in the clinical laboratory: a longitudinal analysis of specimen identification errors.

Science.gov (United States)

Wagar, Elizabeth A; Tamashiro, Lorraine; Yasin, Bushra; Hilborne, Lee; Bruckner, David A

2006-11-01

Patient safety is an increasingly visible and important mission for clinical laboratories. Attention to improving processes related to patient identification and specimen labeling is being paid by accreditation and regulatory organizations because errors in these areas that jeopardize patient safety are common and avoidable through improvement in the total testing process. To assess patient identification and specimen labeling improvement after multiple implementation projects using longitudinal statistical tools. Specimen errors were categorized by a multidisciplinary health care team. Patient identification errors were grouped into 3 categories: (1) specimen/requisition mismatch, (2) unlabeled specimens, and (3) mislabeled specimens. Specimens with these types of identification errors were compared preimplementation and postimplementation for 3 patient safety projects: (1) reorganization of phlebotomy (4 months); (2) introduction of an electronic event reporting system (10 months); and (3) activation of an automated processing system (14 months) for a 24-month period, using trend analysis and Student t test statistics. Of 16,632 total specimen errors, mislabeled specimens, requisition mismatches, and unlabeled specimens represented 1.0%, 6.3%, and 4.6% of errors, respectively. Student t test showed a significant decrease in the most serious error, mislabeled specimens (P patient safety projects. Trend analysis demonstrated decreases in all 3 error types for 26 months. Applying performance-improvement strategies that focus longitudinally on specimen labeling errors can significantly reduce errors, therefore improving patient safety. This is an important area in which laboratory professionals, working in interdisciplinary teams, can improve safety and outcomes of care.

Laboratory directed research and development program FY 2003

Energy Technology Data Exchange (ETDEWEB)

Hansen, Todd

2004-03-27

The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. In FY03, Berkeley Lab was authorized by DOE to establish a funding ceiling for the LDRD program of $15.0 M, which equates to about 3.2% of Berkeley Lab's FY03 projected operating and capital equipment budgets. This funding level was provided to develop new scientific ideas and opportunities and allow the Berkeley Lab Director an opportunity to initiate new directions. Budget constraints limited available resources, however, so only $10.1 M was expended for operating and $0.6 M for capital equipment (2.4% of actual Berkeley Lab FY03 costs). In FY03, scientists submitted 168 proposals, requesting over $24.2 M in operating funding. Eighty-two projects were funded, with awards ranging from $45 K to $500 K. These projects are summarized in Table 1.

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.)