Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

Directory of Open Access Journals (Sweden)

Mark Mario Morando

2018-01-01

Full Text Available Autonomous vehicle (AV technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety impacts are explored through the number of conflicts extracted from the VISSIM traffic microsimulator using the Surrogate Safety Assessment Model (SSAM. Behaviours of human-driven vehicles (HVs and AVs (level 4 automation are modelled within the VISSIM’s car-following model. The safety investigation is conducted for two case studies, that is, a signalised intersection and a roundabout, under various AV penetration rates. Results suggest that AVs improve safety significantly with high penetration rates, even when they travel with shorter headways to improve road capacity and reduce delay. For the signalised intersection, AVs reduce the number of conflicts by 20% to 65% with the AV penetration rates of between 50% and 100% (statistically significant at p<0.05. For the roundabout, the number of conflicts is reduced by 29% to 64% with the 100% AV penetration rate (statistically significant at p<0.05.

78 FR 69603 - Accreditation of Third-Party Auditors/Certification Bodies To Conduct Food Safety Audits and To...

Science.gov (United States)

2013-11-20

... No. FDA-2011-N-0146] RIN 0910-AG66 Accreditation of Third-Party Auditors/Certification Bodies To... entitled ``Accreditation of Third-Party Auditors/Certification Bodies to Conduct Food Safety Audits and to... proposed rule entitled ``Accreditation of Third-Party Auditors/Certification Bodies to Conduct Food Safety...

75 FR 5333 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2010-02-02

...) Place: Embassy Suites Hotel, 1900 Diagonal Road, Alexandria, Virginia 22314, Telephone (703) 684-5900... matters related to the conduct of Study Section business and for the study section to consider safety and...

Safety and injury profile of conducted electrical weapons used by law enforcement officers against criminal suspects.

Science.gov (United States)

Bozeman, William P; Hauda, William E; Heck, Joseph J; Graham, Derrel D; Martin, Brian P; Winslow, James E

2009-04-01

Conducted electrical weapons such as the Taser are commonly used by law enforcement agencies. The safety of these weapons has been the subject of scrutiny and controversy; previous controlled studies in animals and healthy humans may not accurately reflect the risks of conducted electrical weapons used in actual conditions. We seek to determine the safety and injury profile of conducted electrical weapons used against criminal suspects in a field setting. This prospective, multicenter, observational trial tracked a consecutive case series of all conducted electrical weapon uses against criminal suspects at 6 US law enforcement agencies. Mandatory review of each conducted electrical weapon use incorporated physician review of police and medical records. Injuries were classified as mild, moderate, or severe according to a priori definitions. The primary outcome was a composite of moderate and severe injuries, termed significant injuries. Conducted electrical weapons were used against 1,201 subjects during 36 months. One thousand one hundred twenty-five subjects (94%) were men; the median age was 30 years (range 13 to 80 years). Mild or no injuries were observed after conducted electrical weapon use in 1,198 subjects (99.75%; 95% confidence interval 99.3% to 99.9%). Of mild injuries, 83% were superficial puncture wounds from conducted electrical weapon probes. Significant injuries occurred in 3 subjects (0.25%; 95% confidence interval 0.07% to 0.7%), including 2 intracranial injuries from falls and 1 case of rhabdomyolysis. Two subjects died in police custody; medical examiners did not find conducted electrical weapon use to be causal or contributory in either case. To our knowledge, these findings represent the first large, independent, multicenter study of conducted electrical weapon injury epidemiology and suggest that more than 99% of subjects do not experience significant injuries after conducted electrical weapon use.

Determinants for conducting food safety culture research

NARCIS (Netherlands)

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

2016-01-01

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

77 FR 75633 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2012-12-21

... (Closed). 8:00 a.m.-5:00 p.m., February 22, 2013 (Closed). Place: Embassy Suites, 1900 Diagonal Road... conduct of Study Section business and for the study section to consider safety and occupational health...

Contractors’ Attitude towards Enhancing Safety Performance: Case Study on Construction Firms in Penang

Directory of Open Access Journals (Sweden)

Ulang N. Md

2014-01-01

Full Text Available A qualitative study was conducted to investigate the contractors’ attitude towards enhancing the safety performance in construction site. Despite the fact that there are many safety initiatives established by the government, the rates of accidents are still in a critically high condition. Thus the purpose of this research is to study the contractors’ attitude towards enhancing the implementation of safety management system in construction site in order to increase the safety awareness of construction practitioners in construction site and improve the safety condition of construction sites. This study is conducted through oral interviews with the construction practitioners, and visual inspection of construction sites. The attitudes of contractors are evaluated from 3 aspects: Contractors’ efforts in implement and enforce the safety rules, Contractors efforts in overcoming the rate of accidents, and Reasons given by the contractors for not implement safety law.

Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

Report on the results of the safety culture survey conducted in PNRI

International Nuclear Information System (INIS)

Garcia, Corazon M.; Nohay, Carl M.; Badinas, Nelson P.; Melendez, Johnylen V.; Parami, Vangeline K.

2001-01-01

An initial safety culture survey was conducted in the Philippine Nuclear Research Institute (PNRI). Sixty six (66) questionnaires as given in A. Adams and A. Williamson's Measurement of Safety Culture in the Nuclear Industry, UNSW, July 1999 were distributed to the different units of PNRI. The number of sets of survey sheets distributed to the different units corresponded to the number of personnel in the unit based on the information obtained from them. Results were obtained from only 33 respondents. ANSTO has been requested to analyze the results of this survey. While waiting for the results from ANSTO, we attempted to proceed with this analysis in order to learn and practice applying the procedure based on the reference cited above.The respondents from the PNRI showed on the overall neutral views towards safety and their work. Although a minority showed positive responses to safety while a small minority showed negative responses. A remarkable result is that all respondents show strong concern over the welfare of the institute, indicating that there is still a good chance for safety culture to be developed positively among the employees given the proper strategies for motivation. (author)

A multi-site comparison of in vivo safety pharmacology studies conducted to support ICH S7A & B regulatory submissions.

Science.gov (United States)

Ewart, Lorna; Milne, Aileen; Adkins, Debbie; Benjamin, Amanda; Bialecki, Russell; Chen, Yafei; Ericsson, Ann-Christin; Gardner, Stacey; Grant, Claire; Lengel, David; Lindgren, Silvana; Lowing, Sarah; Marks, Louise; Moors, Jackie; Oldman, Karen; Pietras, Mark; Prior, Helen; Punton, James; Redfern, Will S; Salmond, Ross; Skinner, Matt; Some, Margareta; Stanton, Andrea; Swedberg, Michael; Finch, John; Valentin, Jean-Pierre

2013-01-01

Parts A and B of the ICH S7 guidelines on safety pharmacology describe the in vivo studies that must be conducted prior to first time in man administration of any new pharmaceutical. ICH S7A requires a consideration of the sensitivity and reproducibility of the test systems used. This could encompass maintaining a dataset of historical pre-dose values, power analyses, as well as a demonstration of acceptable model sensitivity and robust pharmacological validation. During the process of outsourcing safety pharmacology studies to Charles River Laboratories, AstraZeneca set out to ensure that models were performed identically in each facility and saw this as an opportunity to review the inter-laboratory variability of these essential models. The five in vivo studies outsourced were the conscious dog telemetry model for cardiovascular assessment, the rat whole body plethysmography model for respiratory assessment, the rat modified Irwin screen for central nervous system assessment, the rat charcoal meal study for gastrointestinal assessment and the rat metabolic cage study for assessment of renal function. Each study was validated with known reference compounds and data were compared across facilities. Statistical power was also calculated for each model. The results obtained indicated that each of the studies could be performed with comparable statistical power and could achieve a similar outcome, independent of facility. The consistency of results obtained from these models across multiple facilities was high thus providing confidence that the models can be run in different facilities and maintain compliance with ICH S7A and B. Copyright © 2013 Elsevier Inc. All rights reserved.

COLD-SAT feasibility study safety analysis

Science.gov (United States)

Mchenry, Steven T.; Yost, James M.

1991-01-01

The Cryogenic On-orbit Liquid Depot-Storage, Acquisition, and Transfer (COLD-SAT) satellite presents some unique safety issues. The feasibility study conducted at NASA-Lewis desired a systems safety program that would be involved from the initial design in order to eliminate and/or control the inherent hazards. Because of this, a hazards analysis method was needed that: (1) identified issues that needed to be addressed for a feasibility assessment; and (2) identified all potential hazards that would need to be controlled and/or eliminated during the detailed design phases. The developed analysis method is presented as well as the results generated for the COLD-SAT system.

International Conference on Harmonisation; Guidance on M3(R2) Nonclinical Safety Studies for the Conduct of Human Clinical Trials and Marketing Authorization for Pharmaceuticals; availability. Notice.

Science.gov (United States)

2010-01-21

The Food and Drug Administration (FDA) is announcing the availability of a guidance entitled "M3(R2) Nonclinical Safety Studies for the Conduct of Human Clinical Trials and Marketing Authorization for Pharmaceuticals.'' The guidance was prepared under the auspices of the International Conference on Harmonisation of Technical Requirements for Registration of Pharmaceuticals for Human Use (ICH). The guidance, which is a revision of an existing guidance, discusses the types of nonclinical studies, their scope and duration, and their relation to the conduct of human clinical trials and marketing authorization for pharmaceuticals. The guidance is intended to facilitate the timely conduct of clinical trials and reduce the unnecessary use of animals and other drug development resources.

Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities

International Nuclear Information System (INIS)

2002-01-01

A well performed and adequately documented safety assessment of a nuclear facility will serve as a basis to determine whether the facility complies with the safety objectives, principles and criteria as stipulated by the national regulatory body of the country where the facility is in operation. International experience shows that the practices and methodologies used to perform safety assessments and periodic safety re-assessment for non-reactor nuclear facilities differ significantly from county to country. Most developing countries do not have methods and guidance for safety assessment that are prescribed by the regulatory body. Typically the safety evaluation for the facility is based on a case by case assessment. Whilst conservative deterministic analyses are predominantly used as a licensing basis in many countries, recently probabilistic safety assessment (PSA) techniques have been applied as a useful complementary tool to support safety decision making. The main benefit of PSA is to provide insights into the safety aspects of facility design and operation. PSA points up the potential environmental impacts of postulated accidents, including the dominant risk contributors, and enables safety analysts to compare options for reducing risk. In order to advise on how to apply PSA methodology for the safety assessment of non-reactor nuclear facilities, the IAEA organized several consultants meetings, which led to the preparation of this TECDOC. This document is intended as guidance for the conduct of PSA in non-nuclear facilities. The main emphasis here is on the general procedural steps of a PSA that is specific for a non-reactor nuclear facility, rather than the details of the specific methods. The report is directed at technical staff managing or performing such probabilistic assessments and to promote a standardized framework, terminology and form of documentation for these PSAs. It is understood that the level of detail implied in the tasks presented in this

Activities on safety culture study. Study status in public and private sectors

International Nuclear Information System (INIS)

Makino, Maomi; Takano, Kenichi

2004-01-01

Around after entering in the 21st century, organizational accidents had occurred in Japan at various industries including nuclear industry, which were caused directly by unsafe action, human error and illegal conduct of personnel but there were problems in safety culture of organization such as slow retreat of safety system stimulated by management, schedule control and procedure management becoming a dead letter, lack of safety education, and workplace climate of schedule priority. This article referred to organizational factors common to many severe accidents and introduced safety culture study in public and private sectors to overcome those factors. Safety Culture Evaluation Support Tool (SCEST) was developed for self-evaluation of safety culture of organization as well as Organizational Reliability model (OR model) for analysis of initiation and propagation process of risk event. Safety diagnosis system and feedback type risk assessment system for promoting safe organizational climate and culture were also developed. (T. Tanaka)

Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

OpenAIRE

Morando, Mark Mario; Tian, Qingyun; Truong, Long T.; Vu, Hai L.

2018-01-01

Autonomous vehicle (AV) technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety...

[Patient safety culture in hospitals: experiences in planning, organising and conducting a survey among hospital staff].

Science.gov (United States)

van Vegten, Amanda; Pfeiffer, Yvonne; Giuliani, Francesca; Manser, Tanja

2011-01-01

This article presents the first hospital-wide survey on patient safety climate, involving all staff (medical and non-medical), in the German-speaking area. Its aim is to share our experiences with planning, organising and conducting this survey. The study was performed at the university hospital in Zurich and had a response rate of 46.8% (2,897 valid questionnaires). The survey instrument ("Patientensicherheitsklimainventar") was based on the Hospital Survey on Patient Safety Culture (AHRQ). Primarily it allowed for assessing the current patient safety climate as well as identifying specific areas for improvement and creating a hospital-wide awareness and acceptance for patient safety issues and interventions (e.g., the introduction of a Critical Incident Reporting System [CIRS]). We discuss the basic principles and the feedback concept guiding the organisation of the overall project. Critical to the success of this project were the guaranteed anonymity of the respondents, adequate communication through well-established channels within the organisation and the commitment of the management across all project phases. Copyright © 2011. Published by Elsevier GmbH.

How the nuclear safety team conducts emergency exercises at the IEA-R1 reactor

International Nuclear Information System (INIS)

Vaz, Antonio C.A.; Silva, Davilson G.; Toyoda, Eduardo Y.; Santia, Paulo S.; Conti, Thadeu N.; Semmler, Renato; Carvalho, Ricardo N.

2015-01-01

This work introduces the Diagram of Emergency Exercise Coordination designed by the Nuclear Safety Team for better Emergency Exercise coordination. The Nuclear Safety Team was created with the mission of avoiding, preventing and mitigating the causes and effects of accidents at the IEA-R1. The facility where we conduct our work is located in an area of a huge population, what increases the responsibility of our mission: conducting exercises and training are part of our daily activities. During the Emergency Exercise, accidents ranked 0-4 on INES (International Nuclear Events Scale) are simulated and involve: Police Department, Fire Department, workers, people from the community, and others. In the last exercise held in June 2014, the scenario contemplated a terrorist organization action that infiltrated in a group of students who were visiting the IEA-R1, tried to steal fresh fuel element to fabricate a dirty bomb. Emergency procedures and plans, timeline and metrics of the actions were applied to the Emergency Exercise evaluation. The next exercise will be held in November, with the simulation of the piping of the primary cooling circuit rupture, causing the emptying of the pool and the lack of cooling of the fuel elements in the reactor core: this will be the scenario. The skills acquired and the systems improvement have been very important tools for the reactor operation safety and the Nuclear Safety Team is making technical efforts so that these Emergency Exercises may be applied to other nuclear and radiological facilities. Equally important for the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human factor in the nuclear safety area, a crucial element that is often not considered by those outside the nuclear sector. Surely, the Diagram of Emergency Exercise Coordination application will improve and facilitate the organization, coordination and evaluation tasks. (author)

How the nuclear safety team conducts emergency exercises at the IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Vaz, Antonio C.A.; Silva, Davilson G.; Toyoda, Eduardo Y.; Santia, Paulo S.; Conti, Thadeu N.; Semmler, Renato; Carvalho, Ricardo N., E-mail: acavaz@ipen.br, E-mail: dgsilva@ipen.br, E-mail: eytoyoda@ipen.br, E-mail: psantia@ipen.br, E-mail: tnconti@ipen.br, E-mail: rsemmler@ipen.b, E-mail: rncarval@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

This work introduces the Diagram of Emergency Exercise Coordination designed by the Nuclear Safety Team for better Emergency Exercise coordination. The Nuclear Safety Team was created with the mission of avoiding, preventing and mitigating the causes and effects of accidents at the IEA-R1. The facility where we conduct our work is located in an area of a huge population, what increases the responsibility of our mission: conducting exercises and training are part of our daily activities. During the Emergency Exercise, accidents ranked 0-4 on INES (International Nuclear Events Scale) are simulated and involve: Police Department, Fire Department, workers, people from the community, and others. In the last exercise held in June 2014, the scenario contemplated a terrorist organization action that infiltrated in a group of students who were visiting the IEA-R1, tried to steal fresh fuel element to fabricate a dirty bomb. Emergency procedures and plans, timeline and metrics of the actions were applied to the Emergency Exercise evaluation. The next exercise will be held in November, with the simulation of the piping of the primary cooling circuit rupture, causing the emptying of the pool and the lack of cooling of the fuel elements in the reactor core: this will be the scenario. The skills acquired and the systems improvement have been very important tools for the reactor operation safety and the Nuclear Safety Team is making technical efforts so that these Emergency Exercises may be applied to other nuclear and radiological facilities. Equally important for the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human factor in the nuclear safety area, a crucial element that is often not considered by those outside the nuclear sector. Surely, the Diagram of Emergency Exercise Coordination application will improve and facilitate the organization, coordination and evaluation tasks. (author)

Review of studies on criticality safety evaluation and criticality experiment methods

International Nuclear Information System (INIS)

Naito, Yoshitaka; Yamamoto, Toshihiro; Misawa, Tsuyoshi; Yamane, Yuichi

2013-01-01

Since the early 1960s, many studies on criticality safety evaluation have been conducted in Japan. Computer code systems were developed initially by employing finite difference methods, and more recently by using Monte Carlo methods. Criticality experiments have also been carried out in many laboratories in Japan as well as overseas. By effectively using these study results, the Japanese Criticality Safety Handbook was published in 1988, almost the intermediate point of the last 50 years. An increased interest has been shown in criticality safety studies, and a Working Party on Nuclear Criticality Safety (WPNCS) was set up by the Nuclear Science Committee of Organisation Economic Co-operation and Development in 1997. WPNCS has several task forces in charge of each of the International Criticality Safety Benchmark Evaluation Program (ICSBEP), Subcritical Measurement, Experimental Needs, Burn-up Credit Studies and Minimum Critical Values. Criticality safety studies in Japan have been carried out in cooperation with WPNCS. This paper describes criticality safety study activities in Japan along with the contents of the Japanese Criticality Safety Handbook and the tasks of WPNCS. (author)

Patient safety risk factors in minimally invasive surgery : A validation study

NARCIS (Netherlands)

Rodrigues, S.P.; Ter Kuile, M.; Dankelman, J.; Jansen, F.W.

2012-01-01

This study was conducted to adapt and validate a patient safety (PS) framework for minimally invasive surgery (MIS) as a first step in understanding the clinical relevance of various PS risk factors in MIS. Eight patient safety risk factor domains were identified using frameworks from a systems

Procedures for conducting probabilistic safety assessments of nuclear power plants (Level 1)

International Nuclear Information System (INIS)

1992-01-01

This report provides guidance for conducting a Level 1 of probabilistic safety assessment (PSA), that is a PSA concerned with events leading to core damage. The scope of this report is confined to internal initiating events (excluding internal fires and floods). A particular aim is to promote a standardized framework, terminology and form of documentation for PSAs so as to facilitate external review of the results of such studies. The report is divided into the following major sections: management and organization; identification of sources of radioactive releases and accident initiators; accident sequence modelling; data assessment and parameter estimation; accident sequence quantification; documentation of the analysis: display and interpretation of result. 45 refs, 7 figs, 23 tabs

Nitrogen-system safety study: Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

1982-07-01

The Department of Energy has primary responsibility for the safety of operations at DOE-owned nuclear facilities. The guidelines for the analysis of credible accidents are outlined in DOE Order 5481.1. DOE has requested that existing plant facilities and operations be reviewed for potential safety problems not covered by standard industrial safety procedures. This review is being conducted by investigating individual facilities and documenting the results in Safety Study Reports which will be compiled to form the Existing Plant Final Safety Analysis Report which is scheduled for completion in September, 1984. This Safety Study documents the review of the Plant Nitrogen System facilities and operations and consists of Section 4.0, Facility and Process Description, and Section 5.0, Accident Analysis, of the Final Safety Analysis Report format. The existing nitrogen system consists of a Superior Air Products Company Type D Nitrogen Plant, nitrogen storage facilities, vaporization facilities and a distribution system. The system is designed to generate and distribute nitrogen gas used in the cascade for seal feed, buffer systems, and for servicing equipment when exceptionally low dew points are required. Gaseous nitrogen is also distributed to various process auxiliary buildings. The average usage is approximately 130,000 standard cubic feet per day

The impact of health and safety committees. A study based on survey, interview, and Occupational Safety and Health Administration data.

Science.gov (United States)

Boden, L I; Hall, J A; Levenstein, C; Punnett, L

1984-11-01

In a study conducted to determine if the existence of a joint labor-management health and safety committee (HSC) was correlated with either the number of Occupational Safety and Health Administration (OSHA) complaints or hazardousness, as measured by OSHA serious citations, virtually no effect could be detected in a sample of 127 Massachusetts manufacturing firms. At a sample of 13 firms, interviews of HSC members were conducted. Committee attributes and perceptions about committee effectiveness were compared with the number of OSHA complaints and serious citations. There were fewer complaints and fewer serious citations at firms with HSCs that were perceived as effective. Results of the study suggest that the objective attributes of the committee may be less important to its success than the commitment of management and labor to solving workplace safety problems.

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

Energy Technology Data Exchange (ETDEWEB)

Lowe, Andrew; Hayward, Brent (Dedale Asia Pacific, Albert Park VIC 3206 (Australia))

2006-08-15

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated

Code of conduct on the safety and security of radioactive sources

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-01-01

The objectives of the Code of Conduct are, through the development, harmonization and implementation of national policies, laws and regulations, and through the fostering of international co-operation, to: (i) achieve and maintain a high level of safety and security of radioactive sources; (ii) prevent unauthorized access or damage to, and loss, theft or unauthorized transfer of, radioactive sources, so as to reduce the likelihood of accidental harmful exposure to such sources or the malicious use of such sources to cause harm to individuals, society or the environment; and (iii) mitigate or minimize the radiological consequences of any accident or malicious act involving a radioactive source. These objectives should be achieved through the establishment of an adequate system of regulatory control of radioactive sources, applicable from the stage of initial production to their final disposal, and a system for the restoration of such control if it has been lost. This Code relies on existing international standards relating to nuclear, radiation, radioactive waste and transport safety and to the control of radioactive sources. It is intended to complement existing international standards in these areas. The Code of Conduct serves as guidance in general issues, legislation and regulations, regulatory bodies as well as import and export of radioactive sources. A list of radioactive sources covered by the code is provided which includes activities corresponding to thresholds of categories.

Code of conduct on the safety and security of radioactive sources

International Nuclear Information System (INIS)

2004-01-01

The objectives of the Code of Conduct are, through the development, harmonization and implementation of national policies, laws and regulations, and through the fostering of international co-operation, to: (i) achieve and maintain a high level of safety and security of radioactive sources; (ii) prevent unauthorized access or damage to, and loss, theft or unauthorized transfer of, radioactive sources, so as to reduce the likelihood of accidental harmful exposure to such sources or the malicious use of such sources to cause harm to individuals, society or the environment; and (iii) mitigate or minimize the radiological consequences of any accident or malicious act involving a radioactive source. These objectives should be achieved through the establishment of an adequate system of regulatory control of radioactive sources, applicable from the stage of initial production to their final disposal, and a system for the restoration of such control if it has been lost. This Code relies on existing international standards relating to nuclear, radiation, radioactive waste and transport safety and to the control of radioactive sources. It is intended to complement existing international standards in these areas. The Code of Conduct serves as guidance in general issues, legislation and regulations, regulatory bodies as well as import and export of radioactive sources. A list of radioactive sources covered by the code is provided which includes activities corresponding to thresholds of categories

Canadian Consumer Food Safety Practices and Knowledge: Foodbook Study.

Science.gov (United States)

Murray, Regan; Glass-Kaastra, Shiona; Gardhouse, Christine; Marshall, Barbara; Ciampa, Nadia; Franklin, Kristyn; Hurst, Matt; Thomas, M Kate; Nesbitt, Andrea

2017-10-01

Understanding consumers' food safety practices and knowledge supports food safety education for the prevention of foodborne illness. The objective of this study was to describe Canadian consumer food safety practices and knowledge. This study identifies demographic groups for targeted food safety education messaging and establishes a baseline measurement to assess the effectiveness of food safety interventions over time. Questions regarding consumer food safety practices and knowledge were included in a population-based telephone survey, Foodbook, conducted from November 2014 to March 2015. The results were analyzed nationally by age group and by gender. The results showed that approximately 90% of Canadians reported taking the recommended cleaning and separating precautions when handling raw meat to prevent foodborne illness. Only 29% of respondents reported using a food thermometer when cooking any meat, and even fewer (12%) reported using a food thermometer for small cuts of meat such as chicken pieces. The majority (>80%) of Canadians were aware of the foodborne illness risks related to chicken and hamburger, but fewer (poultry.

Safety in conducting subcritical neutron-multiplication measurements in situ (Revision of N16.3-1969) - approved 1975

International Nuclear Information System (INIS)

Anon.

1977-01-01

The standard provides safety guidance for conducting subcritical neutron-multiplication measurements where physical protection of personnel against the consequences of a criticality accident is not provided. The objectives of in situ measurements are either to confirm an adequate safety margin or to improve an estimate of such a margin. The first objective may constitute a test of the criticality safety of a design that is based on calculations. The second may effect improved operating conditions by reducing the uncertainty of safety margins and providing guidance to new designs

Patient safety priorities in mental healthcare in Switzerland: a modified Delphi study.

Science.gov (United States)

Mascherek, Anna C; Schwappach, David L B

2016-08-05

Identifying patient safety priorities in mental healthcare is an emerging issue. A variety of aspects of patient safety in medical care apply for patient safety in mental care as well. However, specific aspects may be different as a consequence of special characteristics of patients, setting and treatment. The aim of the present study was to combine knowledge from the field and research and bundle existing initiatives and projects to define patient safety priorities in mental healthcare in Switzerland. The present study draws on national expert panels, namely, round-table discussion and modified Delphi consensus method. As preparation for the modified Delphi questionnaire, two round-table discussions and one semistructured questionnaire were conducted. Preparative work was conducted between May 2015 and October 2015. The modified Delphi was conducted to gauge experts' opinion on priorities in patient safety in mental healthcare in Switzerland. In two independent rating rounds, experts made private ratings. The modified Delphi was conducted in winter 2015. Nine topics were defined along the treatment pathway: diagnostic errors, non-drug treatment errors, medication errors, errors related to coercive measures, errors related to aggression management against self and others, errors in treatment of suicidal patients, communication errors, errors at interfaces of care and structural errors. Patient safety is considered as an important topic of quality in mental healthcare among experts, but it has been seriously neglected up until now. Activities in research and in practice are needed. Structural errors and diagnostics were given highest priority. From the topics identified, some are overlapping with important aspects of patient safety in medical care; however, some core aspects are unique. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

49 CFR 240.113 - Individual's duty to furnish data on prior safety conduct as an employee of a different railroad.

Science.gov (United States)

2010-10-01

....113 Individual's duty to furnish data on prior safety conduct as an employee of a different railroad... 49 Transportation 4 2010-10-01 2010-10-01 false Individual's duty to furnish data on prior safety conduct as an employee of a different railroad. 240.113 Section 240.113 Transportation Other Regulations...

Code of conduct on the safety and security of radioactive sources

International Nuclear Information System (INIS)

Anon.

2001-01-01

The objective of the code of conduct is to achieve and maintain a high level of safety and security of radioactive sources through the development, harmonization and enforcement of national policies, laws and regulations, and through the fostering of international co-operation. In particular, this code addresses the establishment of an adequate system of regulatory control from the production of radioactive sources to their final disposal, and a system for the restoration of such control if it has been lost. (N.C.)

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

The Development, Content, Design, and Conduct of the 2011 Piloted US DOE Nuclear Criticality Safety Program Criticality Safety Engineering Training and Education Project

International Nuclear Information System (INIS)

Hopper, Calvin Mitchell

2011-01-01

In May 1973 the University of New Mexico conducted the first nationwide criticality safety training and education week-long short course for nuclear criticality safety engineers. Subsequent to that course, the Los Alamos Critical Experiments Facility (LACEF) developed very successful 'hands-on' subcritical and critical training programs for operators, supervisors, and engineering staff. Since the inception of the US Department of Energy (DOE) Nuclear Criticality Technology and Safety Project (NCT and SP) in 1983, the DOE has stimulated contractor facilities and laboratories to collaborate in the furthering of nuclear criticality as a discipline. That effort included the education and training of nuclear criticality safety engineers (NCSEs). In 1985 a textbook was written that established a path toward formalizing education and training for NCSEs. Though the NCT and SP went through a brief hiatus from 1990 to 1992, other DOE-supported programs were evolving to the benefit of NCSE training and education. In 1993 the DOE established a Nuclear Criticality Safety Program (NCSP) and undertook a comprehensive development effort to expand the extant LACEF 'hands-on' course specifically for the education and training of NCSEs. That successful education and training was interrupted in 2006 for the closing of the LACEF and the accompanying movement of materials and critical experiment machines to the Nevada Test Site. Prior to that closing, the Lawrence Livermore National Laboratory (LLNL) was commissioned by the US DOE NCSP to establish an independent hands-on NCSE subcritical education and training course. The course provided an interim transition for the establishment of a reinvigorated and expanded two-week NCSE education and training program in 2011. The 2011 piloted two-week course was coordinated by the Oak Ridge National Laboratory (ORNL) and jointly conducted by the Los Alamos National Laboratory (LANL) classroom education and facility training, the Sandia National

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

International Nuclear Information System (INIS)

Lowe, Andrew; Hayward, Brent

2006-08-01

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated results of the

Fusion-reactor blanket-material safety-compatibility studies

International Nuclear Information System (INIS)

Jeppson, D.W.; Muhlestein, L.D.; Keough, R.F.; Cohen, S.

1982-11-01

Blanket material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Blanket material safety compatibility studies are being conducted to identify and characterize blanket-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate that : (1) ternary oxides (LiAlO 2 , Li 2 ZrO 3 , Li 2 SiO 3 , Li 4 SiO 4 and LiTiO 3 ) at postulated blanket operating temperatures are compatible with water coolant, while liquid lithium and Li 7 Pb 2 alloy reactions with water generate heat, aerosol and hydrogen; (2) lithium oxide and Li 17 Pb 83 alloy react mildly with water requiring special precautions to control hydrogen release; (3) liquid lithium reacts substantially, while Li 17 Pb 83 alloy reacts mildly with concrete to produce hydrogen; and (4) liquid lithium-air reactions present some major safety concerns

Safety study application guide

International Nuclear Information System (INIS)

1993-07-01

Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly open-quotes lowclose quotes) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, open-quotes Technical Safety Requirements,close quotes and 5480.23, open-quotes Nuclear Safety Analysis Reports.close quotes A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis

Modeling the Relationship between Safety Climate and Safety Performance in a Developing Construction Industry: A Cross-Cultural Validation Study.

Science.gov (United States)

Zahoor, Hafiz; Chan, Albert P C; Utama, Wahyudi P; Gao, Ran; Zafar, Irfan

2017-03-28

This study attempts to validate a safety performance (SP) measurement model in the cross-cultural setting of a developing country. In addition, it highlights the variations in investigating the relationship between safety climate (SC) factors and SP indicators. The data were collected from forty under-construction multi-storey building projects in Pakistan. Based on the results of exploratory factor analysis, a SP measurement model was hypothesized. It was tested and validated by conducting confirmatory factor analysis on calibration and validation sub-samples respectively. The study confirmed the significant positive impact of SC on safety compliance and safety participation , and negative impact on number of self-reported accidents/injuries . However, number of near-misses could not be retained in the final SP model because it attained a lower standardized path coefficient value. Moreover, instead of safety participation , safety compliance established a stronger impact on SP. The study uncovered safety enforcement and promotion as a novel SC factor, whereas safety rules and work practices was identified as the most neglected factor. The study contributed to the body of knowledge by unveiling the deviations in existing dimensions of SC and SP. The refined model is expected to concisely measure the SP in the Pakistani construction industry, however, caution must be exercised while generalizing the study results to other developing countries.

Preliminary Study on the Development of Quantitative Safety Culture Index

International Nuclear Information System (INIS)

Lee, Young Eal; Kim, Hun Sil; Ahn, Nam Sung

2005-01-01

Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. Because it needs to be recognized as the most significant consciousness to achieve the nuclear safety performance, Korean government and nuclear power generation company have tried to develop the practical method to improve the safety culture from the long term point view. In this study, based on the site interviews to define the potential issues on organizational behavior for the safe operation and the survey on the level of safety culture of occupied workers are conducted. Survey results are quantified as a few indicators of nuclear safety by the statistical method and it can be simulated by the dynamic modeling as time goes on. Currently index and dynamic modeling are still being developed, however, results can be used to suggest the long term strategy which safety is clearly integrated into all activities in the nuclear organization

Safety studies conducted on pecan shell fiber, a food ingredient produced from ground pecan shells

OpenAIRE

Dolan, Laurie; Matulka, Ray; Worn, Jeffrey; Nizio, John

2015-01-01

Use of pecan shell fiber in human food is presently limited, but could increase pending demonstration of safety. In a 91-day rat study, pecan shell fiber was administered at dietary concentrations of 0 (control), 50 000, 100 000 or 150 000 ppm. There was no effect of the ingredient on body weight of males or females or food consumption of females. Statistically significant increases in food consumption were observed throughout the study in 100 000 and 150 000 ppm males, resulting in intermitt...

75 FR 3471 - International Conference on Harmonisation; Guidance on M3(R2) Nonclinical Safety Studies for the...

Science.gov (United States)

2010-01-21

...] International Conference on Harmonisation; Guidance on M3(R2) Nonclinical Safety Studies for the Conduct of... the availability of a guidance entitled ``M3(R2) Nonclinical Safety Studies for the Conduct of Human... auspices of the International Conference on Harmonisation of Technical Requirements for Registration of...

The reactor safety study of experimental multi-purpose VHTR design

International Nuclear Information System (INIS)

Yasuno, T.; Mitake, S.; Ezaki, M.; Suzuki, K.

1981-01-01

Over the past years, the design works of the Experimental Very High Temperature Reactor (VHTR) plant have been conducted at Japan Atomic Energy Research Institute. The conceptual design has been completed and the more detailed design works and the safety analysis of the experimental VHTR plant are continued. The purposes of design studies are to show the feasibility of the experimental VHTR program, to specify the characteristics and functions of the plant components, to point out the R and D items necessary for the experimental VHTR plant construction, and to analyze the feature of the plant safety. In this paper the summary of system design and safety features of the experimental reactor are indicated. Main issues are the safety philosophy for the design basis accident, the accidents assumed and the engineered safety systems adopted in the design works

Patient safety challenges in a case study hospital--of relevance for transfusion processes?

Science.gov (United States)

Aase, Karina; Høyland, Sindre; Olsen, Espen; Wiig, Siri; Nilsen, Stein Tore

2008-10-01

The paper reports results from a research project with the objective of studying patient safety, and relates the finding to safety issues within transfusion medicine. The background is an increased focus on undesired events related to diagnosis, medication, and patient treatment in general in the healthcare sector. The study is designed as a case study within a regional Norwegian hospital conducting specialised health care services. The study includes multiple methods such as interviews, document analysis, analysis of error reports, and a questionnaire survey. Results show that the challenges for improved patient safety, based on employees' perceptions, are hospital management support, reporting of accidents/incidents, and collaboration across hospital units. Several of these generic safety challenges are also found to be of relevance for a hospital's transfusion service. Positive patient safety factors are identified as teamwork within hospital units, a non-punitive response to errors, and unit manager's actions promoting safety.

Independent safety organization

International Nuclear Information System (INIS)

Kato, W.Y.; Weinstock, E.V.; Carew, J.F.; Cerbone, R.J.; Guppy, J.G.; Hall, R.E.; Taylor, J.H.

1985-01-01

Brookhaven National Laboratory has conducted a study on the need and feasibility of an independent organization to investigate significant safety events for the Office for Analysis and Evaluation of Operational Data, USNRC. The study consists of three parts: the need for an independent organization to investigate significant safety events, alternative organizations to conduct investigations, and legislative requirements. The determination of need was investigated by reviewing current NRC investigation practices, comparing aviation and nuclear industry practices, and interviewing a spectrum of representatives from the nuclear industry, the regulatory agency, and the public sector. The advantages and disadvantages of alternative independent organizations were studied, namely, an Office of Nuclear Safety headed by a director reporting to the Executive Director for Operations (EDO) of NRC; an Office of Nuclear Safety headed by a director reporting to the NRC Commissioners; a multi-member NTSB-type Nuclear Safety Board independent of the NRC. The costs associated with operating a Nuclear Safety Board were also included in the study. The legislative requirements, both new authority and changes to the existing NRC legislative authority, were studied. 134 references

Lessons learned on the design and the conduct of Post-Authorization Safety Studies

DEFF Research Database (Denmark)

Engel, Pierre; Almas, Mariana Ferreira; De Bruin, Marieke Louise

2017-01-01

Aims: To describe and characterize the first cohort of Post-Authorization Safety Study (PASS) protocols reviewed under the recent European pharmacovigilance legislation. Methods: A systematic approach was used to compile all publicly available information on PASS protocols and assessments submitted...... the 189 PASS, slightly more involved primary data capture (58%). PASS assessing drug utilization mainly leveraged secondary data sources (58%). The majority of the PASS did not include a comparator (65%) and 35% of PASS also evaluated clinical effectiveness endpoints. Conclusions: To the best of our...... knowledge this is the first comprehensive review of three years of PASS protocols submitted under the new pharmacovigilance legislation. Our results show that both EMA and PASS sponsors could respectively increase the availability of protocol assessments and documents in the EU-PAS. Protocol content review...

International assessment of application of the Code of Conduct on the Safety of Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Shokr, A.M. [Atomic Energy Authority, Abouzabal (Egypt). Egypt Second Research Reactor

2015-11-15

The self-assessments performed by thirty-eight countries on application of the Code of Conduct on the Safety of Research Reactors were analyzed and discussed. The results of this analysis were used to identify areas of satisfactory application of the Code and area needing improvements, and therefore require more attention worldwide. The results showed improvement in application of the Code provisions; notably in aging management, regulatory supervision, and consideration of human factors. However, there is a continuing need for further improvement in these areas, as well as in operational radiation protection, emergency preparedness and decommissioning planning. Additionally, increased attention needs to be given to periodic safety reviews, evaluation of site-specific hazards, and assessment of extreme external events. The results showed consistency with the feedback from other sources of information on generic safety issues for research reactors.

International assessment of application of the Code of Conduct on the Safety of Research Reactors

International Nuclear Information System (INIS)

Shokr, A.M.

2015-01-01

The self-assessments performed by thirty-eight countries on application of the Code of Conduct on the Safety of Research Reactors were analyzed and discussed. The results of this analysis were used to identify areas of satisfactory application of the Code and area needing improvements, and therefore require more attention worldwide. The results showed improvement in application of the Code provisions; notably in aging management, regulatory supervision, and consideration of human factors. However, there is a continuing need for further improvement in these areas, as well as in operational radiation protection, emergency preparedness and decommissioning planning. Additionally, increased attention needs to be given to periodic safety reviews, evaluation of site-specific hazards, and assessment of extreme external events. The results showed consistency with the feedback from other sources of information on generic safety issues for research reactors.

A study on safety climate at nuclear power plants

International Nuclear Information System (INIS)

Fukui, Hirokazu; Yoshida, Michio; Yoshiyama, Naohiro

2001-01-01

In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks.' Hence, we have decided to use these three organizational environment

Simulation study of coal mine safety investment based on system dynamics

Institute of Scientific and Technical Information of China (English)

Tong Lei; Dou Yuanyuan

2014-01-01

To generate dynamic planning for coal mine safety investment, this study applies system dynamics to decision-making, classifying safety investments by accident type. It validates the relationship between safety investments and accident cost, by structurally analyzing the causality between safety investments and their influence factors. Our simulation model, based on Vensim software, conducts simulation anal-ysis on a series of actual data from a coalmine in Shanxi Province. Our results indicate a lag phase in safety investments, and that increasing pre-phase safety investment reduces accident costs. We found that a 24%increase in initial safety investment could help reach the target accident costs level 14 months earlier. Our simulation test included nine kinds of variation trends of accident costs brought by different investment ratios on accident prevention. We found an optimized ratio of accident prevention invest-ments allowing a mine to reach accident cost goals 4 months earlier, without changing its total investment.

Premarket safety and efficacy studies for ADHD medications in children.

Directory of Open Access Journals (Sweden)

Florence T Bourgeois

Full Text Available Attention-deficit hyperactivity disorder (ADHD is a chronic condition and pharmacotherapy is the mainstay of treatment, with a variety of ADHD medications available to patients. However, it is unclear to what extent the long-term safety and efficacy of ADHD drugs have been evaluated prior to their market authorization. We aimed to quantify the number of participants studied and their length of exposure in ADHD drug trials prior to marketing.We identified all ADHD medications approved by the Food and Drug Administration (FDA and extracted data on clinical trials performed by the sponsor and used by the FDA to evaluate the drug's clinical efficacy and safety. For each ADHD medication, we measured the total number of participants studied and the length of participant exposure and identified any FDA requests for post-marketing trials.A total of 32 clinical trials were conducted for the approval of 20 ADHD drugs. The median number of participants studied per drug was 75 (IQR 0, 419. Eleven drugs (55% were approved after <100 participants were studied and 14 (70% after <300 participants. The median trial length prior to approval was 4 weeks (IQR 2, 9, with 5 (38% drugs approved after participants were studied <4 weeks and 10 (77% after <6 months. Six drugs were approved with requests for specific additional post-marketing trials, of which 2 were performed.Clinical trials conducted for the approval of many ADHD drugs have not been designed to assess rare adverse events or long-term safety and efficacy. While post-marketing studies can fill in some of the gaps, better assurance is needed that the proper trials are conducted either before or after a new medication is approved.

Safety training parks – A case study on the effectiveness of the trainings

DEFF Research Database (Denmark)

Räsänen, Tuula; Sormunen, E.; Reiman, Arto

The Safety Training Park (STP) concept is a unique Finnish safety training innovation. The STP provides different actors of the construction industry and other branches a practical occupational safety and health (OSH) training area. To the authors’ knowledge, no such parks exist in Europe besides...... Finland. Objec-tive was to study the effectiveness of the STP trainings at a large case company which participated in this study and which has actively trained its personnel in the park. The study was conducted from February 2015 to Feb-ruary 2017. Several key success factors were identified...... in the interviews of this case study. In addition, the company OSH statistics (2010 – 2016) showed a positive development at safety level. However, The Nordic Safety Climate Questionnaire did not show any significant change of results in a one year period. According to the results of the group interviews...

Conduct and results of the Interagency Nuclear Safety Review Panel's evaluation of the Ulysses space mission

International Nuclear Information System (INIS)

Sholtis, J.A. Jr.; Gray, L.B.; Huff, D.A.; Klug, N.P.; Winchester, R.O.

1991-01-01

The recent 6 October 1990 launch and deployment of the nuclear-powered Ulysses spacecraft from the Space Shuttle Discovery culminated an extensive safety review and evaluation effort by the Interagency Nuclear Safety Review Panel (INSRP). After more than a year of detailed independent review, study, and analysis, the INSRP prepared a Safety Evaluation Report (SER) on the Ulysses mission, in accordance with Presidential Directive-National Security Council memorandum 25. The SER, which included a review of the Ulysses Final Safety Analysis Report (FSAR) and an independent characterization of the mission risks, was used by the National Aeronautics and Space Administration (NASA) in its decision to request launch approval as well as by the Executive Office of the President in arriving at a launch decision based on risk-benefit considerations. This paper provides an overview of the Ulysses mission and the conduct as well as the results of the INSRP evaluation. While the mission risk determined by the INSRP in the SER was higher than that characterized by the Ulysses project in the FSAR, both reports indicated that the radiological risks were relatively small. In the final analysis, the SER proved to be supportive of a positive launch decision. The INSRP evaluation process has demonstrated its effectiveness numerous times since the 1960s. In every case, it has provided the essential ingredients and perspective to permit an informed launch decision at the highest level of our Government

Self-assessment of application of the Code of Conduct on the safety of research reactors - Mexico

International Nuclear Information System (INIS)

Mamani-Alegria, Y.R.; Salgado-Gonzalez, J.R.; Miranda-Aldaco, J.

2009-01-01

In Mexico, the nuclear regulatory body is the National Commission on Nuclear Safety and Safeguards (CNSNS), and there is one research reactor, a TRIGA MARK III, operated by the National Institute for Nuclear Research (ININ). The main aspects of the Self-assessment of application of The Code of Conduct on the Safety of Research Reactor are given for the case of the TRIGA reactor. Furthermore, in this paper we give a brief description of the legal framework of the licensing process, for nuclear activities in a research reactor, there are also highlights of the major reactor features, the uses of the reactor for isotope production, the management and verification of safety, the radiation protection management program, the emergency planning and the training and qualification of the operation personnel. (author)

A study on safety climate at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fukui, Hirokazu [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Yoshida, Michio; Yoshiyama, Naohiro [Japan Institute for Group Dynamics, Fukuoka (Japan)

2001-09-01

In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety

Conceptual design study for the demonstration reactor of JSFR. (3) Safety design and evaluation

International Nuclear Information System (INIS)

Tani, Akihiro; Shimakawa, Yoshio; Kubo, Shigenobu; Fujimura, Ken; Yamano, Hidemasa

2011-01-01

This paper describes the result of conceptual safety design and evaluation for the demonstration plant of Japan sodium-cooled fast reactor (JSFR), which was preliminarily conducted for providing information necessary to decide the plant specification for further design study. The plant major specifications except for output power and safety design concept are almost the same as those of the commercial JSFR. A set of safety evaluation for typical design basis events (DBEs) is mainly focused here, which was conducted for the 750 MWe design. Safety analyses for DBEs evaluation were performed on the basis of conservative assumptions using a one-dimensional flow network code with point kinetics. For representative DBEs, transient over power type events and loss of flow type events were analyzed. The long-term loss-of-offsite power event was also calculated to evaluate the natural circulation decay heat removal system. All analytical results showed to meet tentative safety criteria, thus it was confirmed that the safety design concept of JSFR is feasible against DBEs. (author)

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.)

Research study about the establishment of safety culture. Effects of organizational factors in construction industry's safety indices

International Nuclear Information System (INIS)

Kojima, Mitsuhiro; Hirose, Humiko; Takano, Kenichi; Hasegawa, Naoko

1999-01-01

To find the relationships between safety related activities (such as safety patrol' or '4s/5s activities') and accidents rate in the workplace, questionnaires were sent to 965 construction companies and 120 answers were returned. In this questionnaire, safety activities, safety regulations and safety policies of the companies were asked and organizational climates, company policies, philosophies and the number of accidents in workplace were also asked. There seems some relationships between accidents rate and safety activities, safety regulations and safety policies in the companies, but the deviations between estimate values and observed values are so great that it seems impossible to estimate the accidents rate in the working place from the safety activities, safety regulations and safety policies of the companies. On the other hand, some characteristics of safety activities and organizational climates in the construction industry were identified using multi variants analysis. More detailed researches using sophisticated questionnaire will be conducted in the construction industry and petrochemical industry and relationships between the accidents rate and the safety activities will be compared between different industries. (author)

Patients for patient safety in China: a cross sectional study.

Science.gov (United States)

Zhang, Qiongwen; Li, Yulin; Li, Jing; Mao, Xuanyue; Zhang, Lijuan; Ying, Qinghua; Wei, Xin; Shang, Lili; Zhang, Mingming

2012-02-01

To investigate the baseline status of patients' awareness, knowledge, and attitudes to patient safety in China, and to determine the factors that influence patients' involvement in patient safety. We conducted a cross sectional survey using questionnaires adapted from recent studies on patient safety from outside China. The items included medical errors, infection, medication safety, and other aspects of patient safety. The questionnaire included 17 items and 5 domains. The survey was conducted between Jan. 2009 and Dec. 2010 involving 1000 patients from ten grade-A hospitals in seven provinces or cities in China. Most patients from the surgery departments completed the questionnaires voluntarily and anonymously. Five reviewers independently input the data into Microsoft Excel 2003, and the data were double-checked. Data were analyzed using SPSS 15.0 software for differences in the perceptions and attitudes of patients toward patient safety among different genders, ages, and regions. We distributed 1000 questionnaires and collected 959 completed questionnaires (response rate: 96%). Among the respondents, 58% of patients did not know what medical error is. Sixty-five percent of patients wanted disclosure of all medical errors. After errors occurred, 58% of patients wanted explanations of all possible harms that had resulted. Among 187 patients who had experienced medical errors, 83% of patients had sought appropriate legal action. About 52% of patients understood hospital infection, but 28% patients did not know that infections could occur in hospital. Seventy-eight percent of patients thought that medical staff should wash their hands before examining patients. More than half of the patients (68%) were willing to remind the staff of hygiene if they saw unsanitary conditions in a health clinic. Only 14% of patients knew the side effects of medications that they took. The majority of patients surveyed expressed willingness to contribute to patient safety, but their

Consumer purchase habits and views on food safety: A Brazilian study

NARCIS (Netherlands)

Behrens, J.H.; Barcellos, M.N.; Frewer, L.J.; Nunes, T.P.; Franco, B.D.G.M.; Destro, M.T.; Landgraf, M.

2010-01-01

This study aimed to evaluate the attitudes towards food safety among consumers in the city of São Paulo, the major consumer market in Brazil. Focus group sessions were conducted with 30 adults responsible for food choices and purchases. Results indicated a preference for supermarkets over street

Improving safety culture through the health and safety organization: a case study.

Science.gov (United States)

Nielsen, Kent J

2014-02-01

International research indicates that internal health and safety organizations (HSO) and health and safety committees (HSC) do not have the intended impact on companies' safety performance. The aim of this case study at an industrial plant was to test whether the HSO can improve company safety culture by creating more and better safety-related interactions both within the HSO and between HSO members and the shop-floor. A quasi-experimental single case study design based on action research with both quantitative and qualitative measures was used. Based on baseline mapping of safety culture and the efficiency of the HSO three developmental processes were started aimed at the HSC, the whole HSO, and the safety representatives, respectively. Results at follow-up indicated a marked improvement in HSO performance, interaction patterns concerning safety, safety culture indicators, and a changed trend in injury rates. These improvements are interpreted as cultural change because an organizational double-loop learning process leading to modification of the basic assumptions could be identified. The study provides evidence that the HSO can improve company safety culture by focusing on safety-related interactions. © 2013. Published by Elsevier Ltd and National Safety Council.

Study on the KALIMER safety approach

International Nuclear Information System (INIS)

Kim, Eui Kwang; Han, Do Hee; Kim, Young Cheol.

1997-01-01

This study describes KALIMER's safety approach, how to establish the safety criteria and temperature limit, how to define safety evaluation events, and some safety research and development needs items. It is recommended that the KALIMER's approach to safety use seven levels of safety design and a defense-in-depth design approach with particular emphasis on inherent passive features. In order to establish as set DBEs for KALIMER safety evaluation, the procedure is explained how to define safety evaluation events. Final selection is to be determined later with the final establishment of design concepts. On the basis of preliminary studies and evaluation of the plant safety related areas, the KALIMER and PRISM have following three main difference that may require special research and development for KALIMER. (author). 7 refs., 6 tabs., 6 figs

Analysis of Electrical Safety Conditions Taking into Account Soil Conductivity Determined on the Basis of Fuzzy Logic

OpenAIRE

Manusov, V.Z.; Zaytseva, N.M.

2017-01-01

The goal of this work is to prove a possibility of determining soil parameters that influence its conductivity being the basis of grounding, step voltage and touch voltage calculation. This in its turn increases the safety level of electric equipment operation. The article is devoted to development of new, no conventional models of soil conductivity using the theory of fuzzy sets and fuzzy logic. The description of the solution includes the following sections: fuzzy models of specific electri...

78 FR 45781 - Accreditation of Third-Party Auditors/Certification Bodies to Conduct Food Safety Audits and to...

Science.gov (United States)

2013-07-29

... Drug Administration 21 CFR Part 1 and 16 Accreditation of Third-Party Auditors/Certification Bodies to... Accreditation of Third-Party Auditors/Certification Bodies to Conduct Food Safety Audits and to Issue... Administration (FDA) is amending its regulations to provide for accreditation of third-party auditors...

Why is patient safety so hard? A selective review of ethnographic studies.

Science.gov (United States)

Dixon-Woods, Mary

2010-01-01

Ethnographic studies are valuable in studying patient safety. This is a narrative review of four reports of ethnographic studies of patient safety in UK hospitals conducted as part of the Patient Safety Research Programme. Three of these studies were undertaken in operating theatres and one in an A&E Department. The studies found that hospitals were rarely geared towards ensuring perfect performances. The coordination and mobilization of the large number of inter-dependent processes and resources needed to support the achievement of tasks was rarely optimal. This produced significant strain that staff learned to tolerate by developing various compensatory strategies. Teamwork and inter-professional communication did not always function sufficiently well to ensure that basic procedural information was shared or that the required sequence of events was planned. Staff did not always do the right things, for a wide range of different reasons, including contestations about what counted as the right thing. Structures of authority and accountability were not always clear or well-functioning. Patient safety incidents were usually not reported, though there were many different reasons for this. It can be concluded that securing patient safety is hard. There are multiple interacting influences on safety, and solutions need to be based on a sound understanding of the nature of the problems and which approaches are likely to be best suited to resolving them. Some solutions that appear attractive and straightforward are likely to founder. Addressing safety problems requires acknowledgement that patient safety is not simply a technical issue, but a site of organizational and professional politics.

Communication's Role in Safety Management and Performance for the Road Safety Practices

OpenAIRE

Salim Keffane (s)

2014-01-01

Communication among organizations could play an important role in increasing road safety. To get in-depth knowledge of its role, this study measured managers' and employees' perceptions of the communication's role on six safety management and performance criteria for road safety practices by conducting a survey using a questionnaire among 165 employees and 135 managers. Path analysis using AMOS-19 software shows that some of the safety management road safety practices have high correlation wi...

High-temperature gas-cooled reactor safety studies. Progress report for January 1, 1974--June 30, 1975

International Nuclear Information System (INIS)

Cole, T.E.; Sanders, J.P.; Kasten, P.R.

1977-07-01

Progress is reported in the following areas: systems and safety analysis; fission product technology; primary coolant technology; seismic and vibration technology; confinement components; primary system materials technology; safety instrumentation; loss of flow accident analysis using HEATUP code; use of coupled-conduction-convection model for core thermal analysis; development of multichannel conduction-convection program HEXEREI; cooling system performance after shutdown; core auxiliary cooling system performance; development of FLODIS code; air ingress into primary systems following DBDA; performance of PCRV thermal barrier cover plates; temperature limits for fuel particle coating failure; tritium distribution and release in HTGR; energy release to PCRV during DBDA; and mathematical models for HTGR reactor safety studies

Behavior-based safety on construction sites: a case study.

Science.gov (United States)

Choudhry, Rafiq M

2014-09-01

This work presents the results of a case study and describes an important area within the field of construction safety management, namely behavior-based safety (BBS). This paper adopts and develops a management approach for safety improvements in construction site environments. A rigorous behavioral safety system and its intervention program was implemented and deployed on target construction sites. After taking a few weeks of safety behavior measurements, the project management team implemented the designed intervention and measurements were taken. Goal-setting sessions were arranged on-site with workers' participation to set realistic and attainable targets of performance. Safety performance measurements continued and the levels of performance and the targets were presented on feedback charts. Supervisors were asked to give workers recognition and praise when they acted safely or improved critical behaviors. Observers were requested to have discussions with workers, visit the site, distribute training materials to workers, and provide feedback to crews and display charts. They were required to talk to operatives in the presence of line managers. It was necessary to develop awareness and understanding of what was being measured. In the process, operatives learned how to act safely when conducting site tasks using the designed checklists. Current weekly scores were discussed in the weekly safety meetings and other operational site meetings with emphasis on how to achieve set targets. The reliability of the safety performance measures taken by the company's observers was monitored. A clear increase in safety performance level was achieved across all categories: personal protective equipment; housekeeping; access to heights; plant and equipment, and scaffolding. The research reveals that scores of safety performance at one project improved from 86% (at the end of 3rd week) to 92.9% during the 9th week. The results of intervention demonstrated large decreases in

[Exploratory study of road safety in Brazzaville and Pointe-Noire in Republic of the Congo].

Science.gov (United States)

Batala Mpondo, Georges; Bouanga, Marianne; Saya, Yvette Marie Clarisse; Maurice, Pierre; Burigusa, Guillaume

2014-01-01

Although road accidents in the Congo are reaching alarming levels (2,720 accidents in 2010 and 3,126 accidents in 2011), especially with the massive arrival of "Jakarta" mopeds, no evaluation has been conducted to identify and understand the factors responsible for this problem. This article reports the results of an exploratory study conducted in Brazzaville and Pointe-Noire based on information collected from existing documents and by semidirective questionnaire of people from various sectors able to elucidate the problem of road safety. Using William Haddon's matrix, the parameters investigated were : road user behaviour ; environmental and technological factors ; characteristics of road accident victims ; quality of care ; intervention times and organization of prevention. This study demonstrated the absence of a road safety policy in Congo. It also showed that the main factors responsible for road accidents are behavioural (failure to wear safety belts, failure to comply with road signs, fatigue, use of a telephone while driving, etc.), followed by environmental and technological factors (insufficient traffic lights, absence of sidewalks, disorganized occupation of roads, general state of vehicles). This study shows that, in order to improve road safety in the Congo, it is essential to promote the development of national road safety policies and an action plan, intervention on the determinants of road accidents, and a change of road user behaviours (compulsory use of safety belts, ban on the use of a telephone and smoking while driving, etc.). Effective organization of the management of road accident victims and allocation of a budget to implement a road safety policy are also necessary.

Work Pressure and Safety Behaviors among Health Workers in Ghana: The Moderating Role of Management Commitment to Safety

OpenAIRE

Amponsah-Tawaih, Kwesi; Adu, Michael Appiah

2016-01-01

Background: safety and healthy working environment has received numerous research attention over the years. Majority of these researches seem to have been conducted in the construction industry, with little attention in the health sector. Nonetheless, there are couple of studies conducted in Africa that suggest pressure in hospitals. Therefore the aim of the study was to examine how pressure influence safety behavior in the hospitals. With reference to the relevance of safety behavior in prim...

Development of a New Safety Culture Assessment Method for Nuclear Power Plants (NPPs) (A study to suggest a new safety culture assessment method in nuclear power plants)

International Nuclear Information System (INIS)

Han, Sang Min; Seong, Poong Hyun

2014-01-01

This study is conducted to suggest a new safety culture assessment method in nuclear power plants. Criteria with various existing safety culture analysis methods are united, and reliability analysis methods are applied. The concept of the most representative methods, Fault Tree Analysis (FTA) and Failure Mode and Effect Analysis (FMEA), are adopted to assess safety culture. Through this application, it is expected that the suggested method will bring results with convenience and objectiveness

Development of a New Safety Culture Assessment Method for Nuclear Power Plants (NPPs) (A study to suggest a new safety culture assessment method in nuclear power plants)

Energy Technology Data Exchange (ETDEWEB)

Han, Sang Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

2014-08-15

This study is conducted to suggest a new safety culture assessment method in nuclear power plants. Criteria with various existing safety culture analysis methods are united, and reliability analysis methods are applied. The concept of the most representative methods, Fault Tree Analysis (FTA) and Failure Mode and Effect Analysis (FMEA), are adopted to assess safety culture. Through this application, it is expected that the suggested method will bring results with convenience and objectiveness.

Procedures for conducting common cause failure analysis in probabilistic safety assessment

International Nuclear Information System (INIS)

1992-05-01

The principal objective of this report is to supplement the procedure developed in Mosleh et al. (1988, 1989) by providing more explicit guidance for a practical approach to common cause failures (CCF) analysis. The detailed CCF analysis following that procedure would be very labour intensive and time consuming. This document identifies a number of options for performing the more labour intensive parts of the analysis in an attempt to achieve a balance between the need for detail, the purpose of the analysis and the resources available. The document is intended to be compatible with the Agency's Procedures for Conducting Probabilistic Safety Assessments for Nuclear Power Plants (IAEA, 1992), but can be regarded as a stand-alone report to be used in conjunction with NUREG/CR-4780 (Mosleh et al., 1988, 1989) to provide additional detail, and discussion of key technical issues

Criticality safety (prospect of study in NUCEF)

International Nuclear Information System (INIS)

Itagaki, Masafumi

1996-01-01

Experimental studies of criticality safety are under way using STACY and TRACY in NUCEF. Collection of fundamental data on criticality in a solution system is undergoing with STACY to confirm that the likelihood of criticality safety in the system constructed on the assumption of apparatuses in a reprocessing plant is enough large. Whereas some experiments simulating criticality accidents in a reprocessing plant using TRACY were designed to investigate the behaviors of fuel solution and radioactive matters in order to clarify whether it is possible to safely shut them in the facility even if a critical accident occurs. Both STACY and TRACY reached the criticality in 1995. Up to now a series of criticality experiments have been done using STACY with a core tank φ60 cm and the first periodical examination is now under way. On the other hand, we have a plan using TRACY to investigate the behaviors of nuclear heat solution at a criticality accident, and the releasing, transfer and deposition of radioactive materials. After reaching the criticality for the first, the performance verification test has been conducted. The full-scale study using TRACY is planned to begin in the second half of 1996. (M.N.)

Ferrocyanide safety project ferrocyanide aging studies. Final report

International Nuclear Information System (INIS)

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

1996-06-01

This final report gives the results of the work conducted by Pacific Northwest National Laboratory (PNNL) from FY 1992 to FY 1996 on the Ferrocyanide Aging Studies, part of the Ferrocyanide Safety Project. The Ferrocyanide Safety Project was initiated as a result of concern raised about the safe storage of ferrocyanide waste intermixed with oxidants, such as nitrate and nitrite salts, in Hanford Site single-shell tanks (SSTs). In the laboratory, such mixtures can be made to undergo uncontrolled or explosive reactions by heating dry reagents to over 200 degrees C. In 1987, an Environmental Impact Statement (EIS), published by the U.S. Department of Energy (DOE), Final Environmental Impact Statement, Disposal of Hanford Defense High-Level Transuranic and Tank Waste, Hanford Site, Richland, Washington, included an environmental impact analysis of potential explosions involving ferrocyanide-nitrate mixtures. The EIS postulated that an explosion could occur during mechanical retrieval of saltcake or sludge from a ferrocyanide waste tank, and concluded that this worst-case accident could create enough energy to release radioactive material to the atmosphere through ventilation openings, exposing persons offsite to a short-term radiation dose of approximately 200 mrem. Later, in a separate study (1990), the General Accounting Office postulated a worst-case accident of one to two orders of magnitude greater than that postulated in the DOE EIS. The uncertainties regarding the safety envelope of the Hanford Site ferrocyanide waste tanks led to the declaration of the Ferrocyanide Unreviewed Safety Question (USQ) in October 1990

Procedures for conducting probabilistic safety assessments of nuclear power plants (level 2). Accident progression, containment analysis and estimation of accident source terms

International Nuclear Information System (INIS)

1995-01-01

The present publication on Level 2 PSA is based on a compilation and review of practices in various Member States. It complements Safety Series No. 50-P-4, issued in 1992, on Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 1). Refs, figs and tabs

Focus on the studies in support of fire safety analysis. IRSN modelling approach for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Espargilliere, Julien; Meyrand, Raphael; Vinot, Thierry [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France)

2015-12-15

For a fire safety analysis, in order to comply with nuclear safety goals, a nuclear fuel facility operator has to define the elements important for safety to be maintained, even in the case of a fire. One of the key points of this fire analysis is the assessment of possible fire scenarios in the facility. This paper presents the IRSN method applied to a case study to assess fire scenarios which have the most harmful effects on safety targets. The layout consists in a central room (fire cell) containing three glove boxes with radioactive material and three electrical cabinets. This room is linked to two connecting compartments (the fire cell and these two compartments define the containment cell) and then to two corridors. Each room is equipped with a mechanical ventilation system, and a pressure cascade is established from the corridors to the central room. A fire scenario was studied with fire ignition occurring in an electrical cabinet. This scenario has a set of safety goals (prevention of fire cell and containment device failure, propagation of the fire). This case study was conducted with the IRSN code SYLVIA based on two zones modelling. Safety goals were associated with key parameters and performance criteria to be fulfilled. Modelling assumptions were defined in order to maximize physical effects of the fire. Sensitivity studies were also conducted on key parameters such as oxygen limitation, equivalent-fuel definition. Eventually, a critical analysis of the code models was carried out.

Alternative perspectives of safety in home delivered health care: a sequential exploratory mixed method study.

Science.gov (United States)

Jones, Sarahjane

2016-10-01

The aim of this study was to discover and describe how patients, carers and case management nurses define safety and compare it to the traditional risk reduction and harm avoidance definition of safety. Care services are increasingly being delivered in the home for patients with complex long-term conditions. However, the concept of safety remains largely unexplored. A sequential, exploratory mixed method design. A qualitative case study of the UK National Health Service case management programme in the English UK National Health Service was deployed during 2012. Thirteen interviews were conducted with patients (n = 9) and carers (n = 6) and three focus groups with nurses (n = 17) from three community care providers. The qualitative element explored the definition of safety. Data were subjected to framework analysis and themes were identified by participant group. Sequentially, a cross-sectional survey was conducted during 2013 in a fourth community care provider (patient n = 35, carer n = 19, nurse n = 26) as a form of triangulation. Patients and carers describe safety differently to case management nurses, choosing to focus on meeting needs. They use more positive language and recognize the role they have in safety in home-delivered health care. In comparison, case management nurses described safety similarly to the definitions found in the literature. However, when offered the patient and carer definition of safety, they preferentially selected this definition to their own or the literature definition. Patients and carers offer an alternative perspective on patient safety in home-delivered health care that identifies their role in ensuring safety and is more closely aligned with the empowerment philosophy of case management. © 2016 John Wiley & Sons Ltd.

Safety and usefulness of outreach clinic conducted by pediatric echosonographers

International Nuclear Information System (INIS)

Al Harbi, Badr; Al Akhfash, Ali A.; Al Ghamdi, Abdullah; Al-Mesned, Abdulrahman

2012-01-01

Outreach echocardiographic services led by cardiac sonographers may help district level hospitals in the management of patients suspected to have cardiac anomalies. However, the safety and utility of such an approach is not tested. We retrospectively reviewed our experience of patients seen in the outreach visits by the echocardiographers alone and subsequently reviewed in the pediatric cardiology clinic. Comparison between the diagnosis made by the echocardiographer and the consultant pediatric cardiologist were done. We defined safety as no change in patient management plan between the outreach evaluation and the pediatric cardiology clinic evaluation, and we defined usefulness as being beneficial, serviceable and of practical use. Two senior echocardiographic technicians did 41 clinic visits and over a period of 17 months, 623 patients were seen. Patients less than 3 months of age constitute 63% of the total patients seen. Normal echocardiographic examinations were found in 342 (55%) of patients. These patients were not seen in our cardiology clinic. Abnormal echocardiographic examinations were found in 281 (45%) of patients. Among the 281 patients with abnormal echos in the outreach visits, 251 patients (89.3%) were seen in the pediatric cardiology clinic. Comparing the results of the outreach clinic evaluation to that of the pediatric cardiology clinic, 73 patients (29%) diagnosed to have a minor CHD turned to have normal echocardiographic examinations. In all patients seen in both the outreach clinics and the pediatric tertiary cardiac clinics there was no change in patient's management plan. Outreach clinic conducted by pediatric echo sonographers could be useful and safe. It may help in reducing unnecessary visits to pediatric cardiology clinics, provide parental reassurance, and help in narrowing the differential diagnosis in critically ill patient unable to be transferred to tertiary cardiac centers provided it is done by experienced echosonographers

Nurses' experiences and perspectives on medication safety practices: an explorative qualitative study.

Science.gov (United States)

Smeulers, Marian; Onderwater, Astrid T; van Zwieten, Myra C B; Vermeulen, Hester

2014-04-01

To explore nurses' experiences with and perspectives on preventing medication administration errors. Insight into nurses' experiences with and perspectives on preventing medication administration errors is important and can be utilised to tailor and implement safety practices. A qualitative interview study of 20 nurses in an academic medical centre was conducted between March and December of 2011. Three themes emerged from this study: (1) nurses' roles and responsibilities in medication safety: aside from safe preparation and administration, the clinical reasoning of nurses is essential for medication safety; (2) nurses' ability to work safely: knowledge of risks and nurses' work circumstances influence their ability to work safely; and (3) nurses' acceptance of safety practices: advantages, feasibility and appropriateness are important incentives for acceptance of a safety practice. Nurses' experiences coincide with the assumption that they are in a pre-eminent position to enable safe medication management; however, their ability to adequately perform this role depends on sufficient knowledge to assess the risks of medication administration and on the circumstances in which they work. Safe medication management requires a learning climate and professional practice environment that enables further development of professional nursing skills and knowledge. © 2014 John Wiley & Sons Ltd.

Study on occupational safety and health strategy for Taiwan.

Science.gov (United States)

Chuang, Kuen-Yuan; Su, Teh-Sheng; Kuo, Chao-Yin; Lin, Chien-Liang; Lin, Han-Yu; Yu, Yi-Chun

2009-12-01

The aim of this study was to establish a set of occupational safety and health (OSH) issues and development policies suitable for adoption in Taiwan. A survey was conducted on a sample of 102 experts and 235 industrial work safety personnel in Taiwan for statistical analysis of the general consensus, with the results showing such consensus in 104 individual policy indicators. Our results reveal that the most appropriate targets were considered to be annual 10% reductions in the 'occupational accident disability rate', 'occupational accident injury rate' and 'occupational diseases before 2010'. Responding to the specific question of the appropriate method of achieving a reduction in the number of accidents in Taiwan, the primary consideration for 13.4% of the experts and 10.6% of the industry personnel was 'promoting OSH awareness and enhancing the overall safety culture'. As regards the current OSH policy focus, 11.2% of the experts considered 'improving OSH legislation, standards and systems' to be the most important, whilst 8.9% of the industry personnel felt that 'recognizing work stress, overwork and emerging OSH issues' were the most important.

Nordic studies in reactor safety

International Nuclear Information System (INIS)

Pershagen, N.

1993-01-01

The Nordic Nuclear Safety Research Programme SIK programme in reactor safety is part of a major joint Nordic research effort in nuclear safety. The report summarizes the achievements of the SIK programme, which was carried out during 1990-1993 in collaboration between Nordic nuclear utilities, safety authorities, and research institutes. Three main projects were successfully completed dealing with: 1) development and application of a living PSA concept for monitoring the risk of core damage, and of safety indicators for early warning of possible safety problems; 2) review and intercomparison of severe accident codes, case studies of potential core melt accidents in nordic reactors, development of chemical models for the MAAP code, and outline of a system for computerized accident management support; 3) compilation of information about design and safety features of neighbouring reactors in Germany, Lithuania and Russia, and for naval reactors and nuclear submarines. The report reviews the state-of-the-art in each subject matter as an introduction to the individual project summaries. The main findings of each project are highlighted. The report also contains an overview of reactor safety research in the Nordic countries and a summary of fundamental reactor safety principles. (au) (69 refs.)

Assessment of Safety Condition in One of the Teaching Hospitals in Kermanshah (2015: A Case Study

Directory of Open Access Journals (Sweden)

Masod Ghanbari Kakavand

2016-09-01

Full Text Available Background & Aims of the Study: Many working conditions-related stress factors that can produce injuries and illnesses are important in hospital environments. So, the health and safety of nurses and patients from workplace-induced injuries and illnesses is important. In this study, we have assessed the safety condition of one of the teaching hospitals in Kermanshah (2015. Materials and Methods: This descriptive and cross-sectional study was conducted in one of the teaching hospital of Kermanshah University of medical sciences. For this aim a checklist was prepared based on the Occupational Safety and Health Administration's standards and Part 3 of the manual of National Building Regulations. These checklists comprised (The final checklist had 239 questions of 9 dimensions various sections of safety including; fire safety, building safety, electrical safety, emergency exit routes safety, heating and cooling equipment safety, operating room and laundry room and salty home safety. Eventually, using SPSS 16 and descriptive statistics, data were analyzed. Results: According to the results of this study, 66.6% of the units had poor safety and 33.4% of them were moderately safe. As well as, only ICU and CCU unit, heating and cooling equipment and operational room showed moderate compliance with safety requirements and other sections were poorly complied. Conclusion: The results of this study showed that safety conditions of hospital were not at favorable level. These poor safety statues can jeopardize patients and hospital personnel. Thus some interventions such as improvement of working conditions, compliance with safety acts and implementation of health, safety and environmental management system would be necessary.

The Effect of Individual and Organizational Variables on Patient Safety Culture (PSC: A Case Study on Nurses

Directory of Open Access Journals (Sweden)

Mohammad Khandan

2016-07-01

Full Text Available Background & Aims of the Study: The purpose of the hospital accreditation program is to improve the patients' safety. Prevention of mistakes in medical procedures, patients' safety risk identification and infection prevention besides the patients' safety culture (PSC are the key factors that must be considered in a successful patients' safety program.This study aimed to assess PSC and its association with demographic factors among nurses of a hospital in Qom, Iran. Materials & Methods: This research as a descriptive-analytical andcross-sectional study on the effect of individual and organizational variables on patients' safety culture among nurses was conducted in 2015. The final sample included 106 employees from one of the hospitals located in Qom province of Iran. The questionnaires consisted demographic questions and a valid questionnaire about patients' safety culture. T-test, ANOVA and Pearson correlation were conducted to analyze the data by SPSS V20. Results:The age of nurses was 35.15±10.33 (Mean±SD years. Results showed that the patients' safety climate scoreamongnurseswas 70.15±7.23. In addition, there are significant differences between groups of work shift and also education levels in the viewpoints of patients' safety (p0.05. Conclusions: Although, based on our finding,considered hospital had a suitable situation of patients' safety culture, but it is important to pay attention to continuous improvement in the scope of health care workers and patient safety to achieve criticalmission and visions of organizing. Job selection on the basis of demographic considerations and implementation of an accreditation plan for health care systems are two examples of how occupational safety and health tools can be used to provide quality improvement information for health care organizations such as hospitals.

Measuring Safety Culture on Ships Using Safety Climate: A Study among Indian Officers

Directory of Open Access Journals (Sweden)

Yogendra Bhattacharya

2015-12-01

Full Text Available Workplace safety continues to be an area of concern in the maritime industry due to the international nature of the operations. The effectiveness of extensive legislation to manage shipboard safety remains in doubt. The focus must therefore shift towards the human element - seafarers and their perceptions of safety. The study aims to understand the alignment that exists between safety culture and safety climate on board ships as perceived by seafarers. The underlying factors of safety climate were identified using factor analysis which isolated seven factors - Support on Safety, Organizational Support, Resource Availability, Work Environment, Job Demands, ‘Just’ Culture, and Safety Compliance. The perception of safety level of seafarers was found to be low indicating the existence of misalignments between safety culture values and the actual safety climate. The study also reveals that the safety perceptions of officers employed directly by ship owners and those by managers do not differ significantly, nor do they differ between senior and junior officers. A shift in perspective towards how seafarers themselves feel towards safety might provide more effective solutions – instead of relying on regulations - and indeed aid in reducing incidents on board. This paper details practical suggestions on how to identify the factors that contribute towards a better safety climate on board ships.

Do code of conduct audits improve chemical safety in garment factories? Lessons on corporate social responsibility in the supply chain from Fair Wear Foundation.

Science.gov (United States)

Lindholm, Henrik; Egels-Zandén, Niklas; Rudén, Christina

2016-10-01

In managing chemical risks to the environment and human health in supply chains, voluntary corporate social responsibility (CSR) measures, such as auditing code of conduct compliance, play an important role. To examine how well suppliers' chemical health and safety performance complies with buyers' CSR policies and whether audited factories improve their performance. CSR audits (n = 288) of garment factories conducted by Fair Wear Foundation (FWF), an independent non-profit organization, were analyzed using descriptive statistics and statistical modeling. Forty-three per cent of factories did not comply with the FWF code of conduct, i.e. received remarks on chemical safety. Only among factories audited 10 or more times was there a significant increase in the number of factories receiving no remarks. Compliance with chemical safety requirements in garment supply chains is low and auditing is statistically correlated with improvements only at factories that have undergone numerous audits.

Study on real working performance and overload safety factor of high arch dam

Institute of Scientific and Technical Information of China (English)

2008-01-01

Considering the fact that high arch dams have problems such as complicated stress,high cost,and hazards after being damaged,this paper intends to study the effects of load,material strength,and safety analysis method on dam safety and working performance of arch dams.In this article,the effects of temperature,self weight exaction way and water loading on structure response are first discussed,and a more reasonable way of considering is then put forward.By taking into consideration the mechanical property of materials and comparing the effects of different yield criteria on overloading safety of high arch dams,this paper concludes that brittle characteristics of concrete should be fully considered when conducting safety assessment for high arch dams to avoid overestimating the bearing capacity of the dams.By comparing several typical projects,this paper works out a safety assessment system of multiple safety and relevant engineering analogical analysis methods,which is closer to the actual situation,and thus is able to assess the response of high arch dam structure in a more comprehensive way,elicit the safety coefficients in different situations,and provide a new way of considering the safety assessment of high arch dams.

Expermental Studies of quantitative evaluation using HPLC and safety of Sweet Bee Venom

OpenAIRE

Ki Rok Kwon; Ching Seng Chu; Hee Soo Park; Min Ki Kim; Bae Chun Cha; Eun Lee

2007-01-01

Objectives : This study was conducted to carry out quantitative evaluation and safety of Sweet Bee Venom. Methods : Content analysis was done using HPLC, measurement of LD50 was conducted intravenous, subcutaneous, and intra-muscular injection to the ICR mice. Results : 1. According to HPLC analysis, removal of the enzymes containing phospholipase A2 was successfully rendered on Sweet Bee Venom. And analyzing melittin content, Sweet Bee Venom contained 12% more melittin than Bee Venom. ...

The influence of environmental conditions on safety management in hospitals: a qualitative study.

Science.gov (United States)

Alingh, Carien W; van Wijngaarden, Jeroen D H; Huijsman, Robbert; Paauwe, Jaap

2018-05-02

Hospitals are confronted with increasing safety demands from a diverse set of stakeholders, including governmental organisations, professional associations, health insurance companies, patient associations and the media. However, little is known about the effects of these institutional and competitive pressures on hospital safety management. Previous research has shown that organisations generally shape their safety management approach along the lines of control- or commitment-based management. Using a heuristic framework, based on the contextually-based human resource theory, we analysed how environmental pressures affect the safety management approach used by hospitals. A qualitative study was conducted into hospital care in the Netherlands. Five hospitals were selected for participation, based on organisational characteristics as well as variation in their reputation for patient safety. We interviewed hospital managers and staff with a central role in safety management. A total of 43 semi-structured interviews were conducted with 48 respondents. The heuristic framework was used as an initial model for analysing the data, though new codes emerged from the data as well. In order to ensure safe care delivery, institutional and competitive stakeholders often impose detailed safety requirements, strong forces for compliance and growing demands for accountability. As a consequence, hospitals experience a decrease in the room to manoeuvre. Hence, organisations increasingly choose a control-based management approach to make sure that safety demands are met. In contrast, in case of more abstract safety demands and an organisational culture which favours patient safety, hospitals generally experience more leeway. This often results in a stronger focus on commitment-based management. Institutional and competitive conditions as well as strategic choices that hospitals make have resulted in various combinations of control- and commitment-based safety management. A balanced

Safety and economic study of special trains

International Nuclear Information System (INIS)

Loscutoff, W.V.; Hall, R.J.

1976-01-01

A comparative evaluation is being conducted of the safety and economics of special (35 mph and less) and regular trains for shipment of spent fuels. The approach, pertinent considerations, and results to date are discussed. The preliminary conclusion is that special train requirements have potential for only a small reduction in the accident likelihood, while increasing the cost

Safety studies on LOCA for N.S. Mutsu

International Nuclear Information System (INIS)

Kawasaki, Masayuki; Yaguchi, Shinnosuke

1978-01-01

A number of safety studies are under way concerning the reactor plant of N.S. Mutsu. One such study relates to Loss of Coolant Accidents (LOCA), which has been conducted to cover mainly the two subjects of experiments to ascertain the integrity of stainless steel fuel cladding under the action of the Emergency Core Cooling System (ECCS), and analysis of containment integrity following a LOCA. The stainless steel cladding tests were conducted to test swelling, rupture, oxidation and compression characteristics. Few reports are known to have been published in this domain, so that the present results should prove useful for future studies related to ECCS evaluation analyses on stainless steel fuel cladding. The containment integrity analysis covered variations of containment pressure and temperature following a LOCA, performed separately for short- and long-term periods. Estimates were also made on the changes in the hydrogen concentration present inside the containment after a LOCA. The results obtained should serve in determining the characteristic response to LOCA of marine reactor plants

The Use of Questionnaires in Safety Culture Studies in High Reliability Organizations. Literature Review and an Application in the Spanish Nuclear Sector

International Nuclear Information System (INIS)

German, S.; Navajas, J.; Silla, I.

2014-01-01

This report examines two aspects related to the use of questionnaires in safety culture research conducted in high reliability organizations. First, a literature review of recent studies that address safety culture through questionnaires is presented. Literature review showed that most studies used only questionnaires as a research technique, were cross-sectional, applied paper-based questionnaires, and were conducted in one type of high reliability organization. Second, a research project on safety culture that used electronic surveys in a sample of experts on safety culture is discussed. This project, developed by CISOT-CIEMAT research institute, was carry out in the Spanish nuclear sector and illustrates relevant aspects of the methodological design and administration processes that must be considered to encourage participation in the study.. (Author)

Consumer food handling in the home: a review of food safety studies.

Science.gov (United States)

Redmond, Elizabeth C; Griffith, Christopher J

2003-01-01

Epidemiological data from Europe, North America, Australia, and New Zealand indicate that a substantial proportion of foodborne disease is attributable to improper food preparation practices in consumers' homes. International concern about consumer food safety has prompted considerable research to evaluate domestic food-handling practices. The majority of consumer food safety studies in the last decade have been conducted in the United Kingdom and Northern Ireland (48%) and in the United States (42%). Surveys (questionnaires and interviews), the most frequent means of data collection, were used in 75% of the reviewed studies. Focus groups and observational studies have also been used. One consumer food safety study examined the relationship between pathogenic microbial contamination from raw chicken and observed food-handling behaviors, and the results of this study indicated extensive Campylobacter cross-contamination during food preparation sessions. Limited information about consumers' attitudes and intentions with regard to safe food-handling behaviors has been obtained, although a substantial amount of information about consumer knowledge and self-reported practices is available. Observation studies suggest that substantial numbers of consumers frequently implement unsafe food-handling practices. Knowledge, attitudes, intentions, and self-reported practices did not correspond to observed behaviors, suggesting that observational studies provide a more realistic indication of the food hygiene actions actually used in domestic food preparation. An improvement in consumer food-handling behavior is likely to reduce the risk and incidence of foodborne disease. The need for the development and implementation of food safety education strategies to improve specific food safety behaviors is reviewed in this paper.

Do code of conduct audits improve chemical safety in garment factories? Lessons on corporate social responsibility in the supply chain from Fair Wear Foundation

Science.gov (United States)

2016-01-01

Background In managing chemical risks to the environment and human health in supply chains, voluntary corporate social responsibility (CSR) measures, such as auditing code of conduct compliance, play an important role. Objectives To examine how well suppliers’ chemical health and safety performance complies with buyers’ CSR policies and whether audited factories improve their performance. Methods CSR audits (n = 288) of garment factories conducted by Fair Wear Foundation (FWF), an independent non-profit organization, were analyzed using descriptive statistics and statistical modeling. Results Forty-three per cent of factories did not comply with the FWF code of conduct, i.e. received remarks on chemical safety. Only among factories audited 10 or more times was there a significant increase in the number of factories receiving no remarks. Conclusions Compliance with chemical safety requirements in garment supply chains is low and auditing is statistically correlated with improvements only at factories that have undergone numerous audits. PMID:27611103

Safety inspection guide, Mod III (a systematic approach to conducting a safety inspection)

International Nuclear Information System (INIS)

Davidson, J.E.

1977-06-01

This guide was developed as a comprehensive/systematic approach to the problem of performing a safety inspection. Five basic sections (categories) are considered in the guide: physical work place; machines/mechanical equipment; hazardous materials/processes/environments; energy sources; and management hazard . control factors. The basic concept is that one starts evaluating hazard potentials from the physical work place and continues considering other elements as they are added to the physical work place. This approach provides a better understanding of the interfaces of each section to the entire group. The guide is supported by an Area Safety Inspection Result form to record defects or conditions found, the evaluation (best estimate) of the urgency or priority for correcting deficiencies or areas of noncompliance, and the status of corrective action. Additionally, the guide serves as an educational tool in accident prevention for supervisors and employees

Regulatory review of safety cases and safety assessments - associated challenges

International Nuclear Information System (INIS)

Bennett, D.G.; Ben Belfadhel, M.; Metcalf, P.E.

2006-01-01

Regulatory reviews of safety cases and safety assessments are essential for credible decision making on the licensing or authorization of radioactive waste disposal facilities. Regulatory review also plays an important role in developing the safety case and in establishing stakeholders' confidence in the safety of the facility. Reviews of safety cases for radioactive waste disposal facilities need to be conducted by suitably qualified and experienced staff, following systematic and well planned review processes. Regulatory reviews should be sufficiently comprehensive in their coverage of issues potentially affecting the safety of the disposal system, and should assess the safety case against clearly established criteria. The conclusions drawn from a regulatory review, and the rationale for them should be reproducible and documented in a transparent and traceable way. Many challenges are faced when conducting regulatory reviews of safety cases. Some of these relate to issues of project and programme management, and resources, while others derive from the inherent difficulties of assessing the potential long term future behaviour of engineered and environmental systems. The paper describes approaches to the conduct of regulatory reviews and discusses some of the challenges faced. (author)

Assessment of radiation safety awareness among nuclear medicine nurses: a pilot study

International Nuclear Information System (INIS)

Yunus, N A; Abdullah, M H R O; Said, M A; Ch'ng, P E

2014-01-01

All nuclear medicine nurses need to have some knowledge and awareness on radiation safety. At present, there is no study to address this issue in Malaysia. The aims of this study were (1) to determine the level of knowledge and awareness on radiation safety among nuclear medicine nurses at Putrajaya Hospital in Malaysia and (2) to assess the effectiveness of a training program provided by the hospital to increase the knowledge and awareness of the nuclear medicine nurses. A total of 27 respondents attending a training program on radiation safety were asked to complete a questionnaire. The questionnaire consists 16 items and were categorized into two main areas, namely general radiation knowledge and radiation safety. Survey data were collected before and after the training and were analyzed using descriptive statistics and paired sample t-test. Respondents were scored out of a total of 16 marks with 8 marks for each area. The findings showed that the range of total scores obtained by the nuclear medicine nurses before and after the training were 6-14 (with a mean score of 11.19) and 13-16 marks (with a mean score of 14.85), respectively. Findings also revealed that the mean score for the area of general radiation knowledge (7.59) was higher than that of the radiation safety (7.26). Currently, the knowledge and awareness on radiation safety among the nuclear medicine nurses are at the moderate level. It is recommended that a national study be conducted to assess and increase the level of knowledge and awareness among all nuclear medicine nurses in Malaysia

Assessment of radiation safety awareness among nuclear medicine nurses: a pilot study

Science.gov (United States)

Yunus, N. A.; Abdullah, M. H. R. O.; Said, M. A.; Ch'ng, P. E.

2014-11-01

All nuclear medicine nurses need to have some knowledge and awareness on radiation safety. At present, there is no study to address this issue in Malaysia. The aims of this study were (1) to determine the level of knowledge and awareness on radiation safety among nuclear medicine nurses at Putrajaya Hospital in Malaysia and (2) to assess the effectiveness of a training program provided by the hospital to increase the knowledge and awareness of the nuclear medicine nurses. A total of 27 respondents attending a training program on radiation safety were asked to complete a questionnaire. The questionnaire consists 16 items and were categorized into two main areas, namely general radiation knowledge and radiation safety. Survey data were collected before and after the training and were analyzed using descriptive statistics and paired sample t-test. Respondents were scored out of a total of 16 marks with 8 marks for each area. The findings showed that the range of total scores obtained by the nuclear medicine nurses before and after the training were 6-14 (with a mean score of 11.19) and 13-16 marks (with a mean score of 14.85), respectively. Findings also revealed that the mean score for the area of general radiation knowledge (7.59) was higher than that of the radiation safety (7.26). Currently, the knowledge and awareness on radiation safety among the nuclear medicine nurses are at the moderate level. It is recommended that a national study be conducted to assess and increase the level of knowledge and awareness among all nuclear medicine nurses in Malaysia.

Food safety performance indicators to benchmark food safety output of food safety management systems.

Science.gov (United States)

Jacxsens, L; Uyttendaele, M; Devlieghere, F; Rovira, J; Gomez, S Oses; Luning, P A

2010-07-31

There is a need to measure the food safety performance in the agri-food chain without performing actual microbiological analysis. A food safety performance diagnosis, based on seven indicators and corresponding assessment grids have been developed and validated in nine European food businesses. Validation was conducted on the basis of an extensive microbiological assessment scheme (MAS). The assumption behind the food safety performance diagnosis is that food businesses which evaluate the performance of their food safety management system in a more structured way and according to very strict and specific criteria will have a better insight in their actual microbiological food safety performance, because food safety problems will be more systematically detected. The diagnosis can be a useful tool to have a first indication about the microbiological performance of a food safety management system present in a food business. Moreover, the diagnosis can be used in quantitative studies to get insight in the effect of interventions on sector or governmental level. Copyright 2010 Elsevier B.V. All rights reserved.

ROAD ACCIDENT AND SAFETY STUDY IN SYLHET REGION OF BANGLADESH

Directory of Open Access Journals (Sweden)

B. K. BANIK

2011-08-01

Full Text Available Roads, highways and streets are fundamental infrastructure facilities to provide the transportation for passenger travel and goods movement from one place to another in Sylhet, north–eastern division of Bangladesh with rapid growth of road vehicle, being comparatively developed economic tourist prone area faces severe road traffic accident. Such severe road accidents cause harsh safety hazards on the roads of Sylhet area. This research work presents an overview of the road traffic accident and degraded road safety situation in Sylhet zone which in particular, discusses the key road accident problem characteristics identifying the hazardous roads and spots, most responsible vehicles and related components, conditions of drivers and pedestrians, most victims of accident, effects of accident on society, safety priorities and options available in Sylhet. In this regard, a comprehensive questionnaire survey was conducted on the concerned groups of transportation and detailed accident data was collected from a popular local newspaper. Analysis of the study reveals that Dhaka- Sylhet highway is the most hazardous in road basis and Sylhet Sador thana is the most vulnerable in thana basis in Sylhet region.

Nuclear safety culture and nuclear safety supervision

International Nuclear Information System (INIS)

Chai Jianshe

2013-01-01

In this paper, the author reviews systematically and summarizes up the development process and stage characteristics of nuclear safety culture, analysis the connotation and characteristics of nuclear safety culture, sums up the achievements of our country's nuclear safety supervision, dissects the challenges and problems of nuclear safety supervision. This thesis focused on the relationship between nuclear safety culture and nuclear safety supervision, they are essential differences, but there is a close relationship. Nuclear safety supervision needs to introduce some concepts of nuclear safety culture, lays emphasis on humanistic care and improves its level and efficiency. Nuclear safety supervision authorities must strengthen nuclear safety culture training, conduct the development of nuclear safety culture, make sure that nuclear safety culture can play significant roles. (author)

Experimental Study and Computational Simulations of Key Pebble Bed Thermo-mechanics Issues for Design and Safety

Energy Technology Data Exchange (ETDEWEB)

Tokuhiro, Akira; Potirniche, Gabriel; Cogliati, Joshua; Ougouag, Abderrafi

2014-07-08

An experimental and computational study, consisting of modeling and simulation (M&S), of key thermal-mechanical issues affecting the design and safety of pebble-bed (PB) reactors was conducted. The objective was to broaden understanding and experimentally validate thermal-mechanic phenomena of nuclear grade graphite, specifically, spheres in frictional contact as anticipated in the bed under reactor relevant pressures and temperatures. The contact generates graphite dust particulates that can subsequently be transported into the flowing gaseous coolent. Under postulated depressurization transients and with the potential for leaked fission products to be adsorbed onto graphite 'dust', there is the potential for fission products to escape from the primary volume. This is a design safety concern. Furthermore, earlier safety assessment identified the distinct possibility for the dispersed dust to combust in contact with air if sufficient conditions are met. Both of these phenomena were noted as important to design review and containing uncertainty to warrant study. The team designed and conducted two separate effects tests to study and benchmark the potential dust-generation rate, as well as study the conditions under which a dust explosion may occure in a standardized, instrumented explosion chamber.

Driver characteristics associated with child safety seat usage in Malaysia: a cross-sectional study.

Science.gov (United States)

Kulanthayan, S; Razak, Ahmad; Schenk, Ellen

2010-03-01

The rapidly motorizing environment in Malaysia has made child occupant safety a current public health concern. The usage of child safety seats (CSS) is a widely regarded intervention to enhance child occupant safety, yet no study has been conducted on CSS in Malaysia. This study aims to determine the CSS usage rates in Malaysia and to assess driver characteristics that are associated with CSS usage. Nine variables - urban versus rural study location, age, gender, marital status, educational status, monthly family income, number of children present in the vehicle, distance traveled to the study location, and attitude - were examined through a cross-sectional study of interviewing drivers of 230 vehicles transporting at least one child safety in Malaysia. The results indicate that interventional efforts should focus on educational programs geared toward drivers that are less educated or extended family members who inconsistently transport young children. Furthermore, any educational efforts could be strongly enhanced by legislation mandating the use of CSS. Every effort should be made to thoroughly assess the effectiveness of any educational or legislative activities that are implemented. Copyright 2009 Elsevier Ltd. All rights reserved.

10CFR50.59 safety evaluations

International Nuclear Information System (INIS)

Grime, L.; Page, E.

1987-01-01

As a plant changes from the design phase to the operational phase, new regulations and standards apply. One such regulation is 10CFR50.59 on safety evaluations. Once an operating license is issued, it is mandatory to submit all applicable changes, tests, and experiments to the safety evaluation process. As preparation for this transition, Detroit Edison had procedures in place and conducted personnel training. Reviews of the safety engineering were conducted by the on-site review board. The off-site board delegated detailed reviews of most safety evaluations to the independent safety evaluation group (ISEG). The on-site group review included presentation of complete design packages by engineers. The ISEG and off-site review group's activity focused on safety evaluation. This paper addresses industry trends that were studied, Detroit Edison's recent actions, and industry issues related to 10CFR50.59 safety evaluations

Monitoring antimalarial safety and tolerability in clinical trials: A case study from Uganda

Directory of Open Access Journals (Sweden)

Mpimbaza Arthur

2008-06-01

Full Text Available Abstract Background New antimalarial regimens, including artemisinin-based combination therapies (ACTs, have been adopted widely as first-line treatment for uncomplicated malaria. Although these drugs appear to be safe and well-tolerated, experience with their use in Africa is limited and continued assessment of safety is a priority. However, no standardized guidelines for evaluating drug safety and tolerability in malaria studies exist. A system for monitoring adverse events in antimalarial trials conducted in Uganda was developed. Here the reporting system is described, and difficulties faced in analysing and interpreting the safety results are illustrated, using data from the trials. Case description Between 2002 and 2007, eleven randomized, controlled clinical trials were conducted to compare the efficacy, safety, and tolerability of different antimalarial regimens for treatment of uncomplicated malaria in Uganda. The approach to adverse event monitoring was similar in all studies. A total of 5,614 treatments were evaluated in 4,876 patients. Differences in baseline characteristics and patterns of adverse event reporting were noted between the sites, which limited the ability to pool and analyse data. Clinical failure following antimalarial treatment confounded associations between treatment and adverse events that were also common symptoms of malaria, particularly in areas of lower transmission intensity. Discussion and evaluation Despite prospectively evaluating for adverse events, limitations in the monitoring system were identified. New standardized guidelines for monitoring safety and tolerability in antimalarial trials are needed, which should address how to detect events of greatest importance, including serious events, those with a causal relationship to the treatment, those which impact on adherence, and events not previously reported. Conclusion Although the World Health Organization has supported the development of

Consideration of future safety consequences: a new predictor of employee safety.

Science.gov (United States)

Probst, Tahira M; Graso, Maja; Estrada, Armando X; Greer, Sarah

2013-06-01

Compliance with safety behaviors is often associated with longer term benefits, but may require some short-term sacrifices. This study examines the extent to which consideration of future safety consequences (CFSC) predicts employee safety outcomes. Two field studies were conducted to evaluate the reliability and validity of the newly developed Consideration of Future Safety Consequences (CFSC) scale. Surveys containing the CFSC scale and other measures of safety attitudes, behaviors, and outcomes were administered during working hours to a sample of 128 pulp and paper mill employees; after revising the CFSC scale based on these initial results, follow-up survey data were collected in a second sample of 212 copper miners. In Study I, CFSC was predictive of employee safety knowledge and motivation, compliance, safety citizenship behaviors, accident reporting attitudes and behaviors, and workplace injuries - even after accounting for conscientiousness and demographic variables. Moreover, the effects of CFSC on the variables generally appear to be direct, as opposed to mediated by safety knowledge or motivation. These findings were largely replicated in Study II. CFSC appears to be an important personality construct that may predict those individuals who are more likely to comply with safety rules and have more positive safety outcomes. Future research should examine the longitudinal stability of CFSC to determine the extent to which this construct is a stable trait, rather than a safety attitude amenable to change over time or following an intervention. Copyright © 2013 Elsevier Ltd. All rights reserved.

Perceptions of Psychological and Physical Safety Environments of Information Technology Employees: A Phenomenological Study

Science.gov (United States)

Payne, Sheila C.

2012-01-01

A qualitative phenomenological study was conducted to gain a deeper understanding of psychological and safety environments of an oil and gas multinational enterprise. Twenty information technology professionals were interviewed to explore their feelings, perceptions, beliefs, and values of the phenomenon. The interviews elicited data about facets…

Non-clinical studies in the process of new drug development - Part II: Good laboratory practice, metabolism, pharmacokinetics, safety and dose translation to clinical studies.

Science.gov (United States)

Andrade, E L; Bento, A F; Cavalli, J; Oliveira, S K; Schwanke, R C; Siqueira, J M; Freitas, C S; Marcon, R; Calixto, J B

2016-12-12

The process of drug development involves non-clinical and clinical studies. Non-clinical studies are conducted using different protocols including animal studies, which mostly follow the Good Laboratory Practice (GLP) regulations. During the early pre-clinical development process, also known as Go/No-Go decision, a drug candidate needs to pass through several steps, such as determination of drug availability (studies on pharmacokinetics), absorption, distribution, metabolism and elimination (ADME) and preliminary studies that aim to investigate the candidate safety including genotoxicity, mutagenicity, safety pharmacology and general toxicology. These preliminary studies generally do not need to comply with GLP regulations. These studies aim at investigating the drug safety to obtain the first information about its tolerability in different systems that are relevant for further decisions. There are, however, other studies that should be performed according to GLP standards and are mandatory for the safe exposure to humans, such as repeated dose toxicity, genotoxicity and safety pharmacology. These studies must be conducted before the Investigational New Drug (IND) application. The package of non-clinical studies should cover all information needed for the safe transposition of drugs from animals to humans, generally based on the non-observed adverse effect level (NOAEL) obtained from general toxicity studies. After IND approval, other GLP experiments for the evaluation of chronic toxicity, reproductive and developmental toxicity, carcinogenicity and genotoxicity, are carried out during the clinical phase of development. However, the necessity of performing such studies depends on the new drug clinical application purpose.

Driving behaviours, traffic risk and road safety: comparative study between Malaysia and Singapore.

Science.gov (United States)

Khan, Saif ur Rehman; Khalifah, Zainab Binti; Munir, Yasin; Islam, Talat; Nazir, Tahira; Khan, Hashim

2015-01-01

The present study aims to investigate differences in road safety attitude, driver behaviour and traffic risk perception between Malaysia and Singapore. A questionnaire-based survey was conducted among a sample of Singaporean (n = 187) and Malaysian (n = 313) road users. The data was analysed using confirmatory factor analysis and structural equation modelling applied to measure comparative fit indices of Malaysian and Singaporean respondents. The results show that the perceived traffic risk of Malaysian respondents is higher than Singaporean counterparts. Moreover, the structural equation modelling has confirmed perceived traffic risk performing the role of full mediation between perceived driving skills and perceived road safety for both the countries, while perceived traffic skills was found to perform the role of partial mediation between aggression and anxiety, on one hand, and road safety, on the other hand, in Malaysia and Singapore. In addition, in both countries, a weak correlation between perceived driving skills, aggression and anxiety with perceived road safety was found, while a strong correlation exists with traffic risk perception. The findings of this study have been discussed in terms of theoretical, practical and conceptual implications for both scholars and policy-makers to better understand the young drivers' attitude and behaviour relationship towards road safety measures with a view to future research.

IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

Meta-analysis of surgical safety checklist effects on teamwork, communication, morbidity, mortality, and safety.

Science.gov (United States)

Lyons, Vanessa E; Popejoy, Lori L

2014-02-01

The purpose of this study is to examine the effectiveness of surgical safety checklists on teamwork, communication, morbidity, mortality, and compliance with safety measures through meta-analysis. Four meta-analyses were conducted on 19 studies that met the inclusion criteria. The effect size of checklists on teamwork and communication was 1.180 (p = .003), on morbidity and mortality was 0.123 (p = .003) and 0.088 (p = .001), respectively, and on compliance with safety measures was 0.268 (p teamwork and communication, reduce morbidity and mortality, and improve compliance with safety measures. This meta-analysis is limited in its generalizability based on the limited number of studies and the inclusion of only published research. Future research is needed to examine possible moderating variables for the effects of surgical safety checklists.

To dimension safety valves. Probabilist study

International Nuclear Information System (INIS)

Noel, Robert; Couvreur, Denis

1982-01-01

The gauge of safety valves of a steam pressure apparatus is usually determined according to an operating situation envelope which it is admitted covers all that can happen in reality. For the safety of the dryer-superheaters of turbines in nuclear power stations, Electricite de France and Alsthom-Atlantique made a reliability study; its method is exposed and the results are discussed. Such a study is heavy going and complex, but in return it permits a better quantitative understanding of the various dimension and operating parameters of an installation which condition its safety. It is therefore a source of progress [fr

Identifying research priorities for patient safety in mental health: an international expert Delphi study

Science.gov (United States)

Murray, Kevin; Thibaut, Bethan; Ramtale, Sonny Christian; Adam, Sheila; Darzi, Ara; Archer, Stephanie

2018-01-01

Objective Physical healthcare has dominated the patient safety field; research in mental healthcare is not as extensive but findings from physical healthcare cannot be applied to mental healthcare because it delivers specialised care that faces unique challenges. Therefore, a clearer focus and recognition of patient safety in mental health as a distinct research area is still needed. The study aim is to identify future research priorities in the field of patient safety in mental health. Design Semistructured interviews were conducted with the experts to ascertain their views on research priorities in patient safety in mental health. A three-round online Delphi study was used to ascertain consensus on 117 research priority statements. Setting and participants Academic and service user experts from the USA, UK, Switzerland, Netherlands, Ireland, Denmark, Finland, Germany, Sweden, Australia, New Zealand and Singapore were included. Main outcome measures Agreement in research priorities on a five-point scale. Results Seventy-nine statements achieved consensus (>70%). Three out of the top six research priorities were patient driven; experts agreed that understanding the patient perspective on safety planning, on self-harm and on medication was important. Conclusions This is the first international Delphi study to identify research priorities in safety in the mental field as determined by expert academic and service user perspectives. A reasonable consensus was obtained from international perspectives on future research priorities in patient safety in mental health; however, the patient perspective on their mental healthcare is a priority. The research agenda for patient safety in mental health identified here should be informed by patient safety science more broadly and used to further establish this area as a priority in its own right. The safety of mental health patients must have parity with that of physical health patients to achieve this. PMID:29502096

A Study on the Construct Validity of Safety Culture Oversight Model for Nuclear Power Operating Organization

International Nuclear Information System (INIS)

Jung, Su Jin; Choi, Young Sung; Oh, Jang Jin

2015-01-01

In Korea, the safety policy statement declared in 1994 by government stressed the importance of safety culture and licensees were encouraged to manage and conduct their self-assessments. A change in regulatory position about safety culture oversight was made after the event of SBO cover-up in Kori unit 1 and several subsequent falsification events. Since then KINS has been developing licensee's safety culture oversight system including conceptual framework of oversight, prime focus area for oversight, and specific details on regulatory expectations, all of which are based on defence-in-depth (DiD) safety enhancement approach. Development and gathering of performance data which is related to actual 'safety' of nuclear power plant are needed to identify the relationship between safety culture and safety performance. Authors consider this study as pilot which has a contribution on verifying the construct validity of the model and the effectiveness of survey based research. This is the first attempt that the validity of safety culture oversight model has been investigated with empirical data obtained from Korean nuclear power operating organization

A Study on the Construct Validity of Safety Culture Oversight Model for Nuclear Power Operating Organization

Energy Technology Data Exchange (ETDEWEB)

Jung, Su Jin; Choi, Young Sung; Oh, Jang Jin [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

In Korea, the safety policy statement declared in 1994 by government stressed the importance of safety culture and licensees were encouraged to manage and conduct their self-assessments. A change in regulatory position about safety culture oversight was made after the event of SBO cover-up in Kori unit 1 and several subsequent falsification events. Since then KINS has been developing licensee's safety culture oversight system including conceptual framework of oversight, prime focus area for oversight, and specific details on regulatory expectations, all of which are based on defence-in-depth (DiD) safety enhancement approach. Development and gathering of performance data which is related to actual 'safety' of nuclear power plant are needed to identify the relationship between safety culture and safety performance. Authors consider this study as pilot which has a contribution on verifying the construct validity of the model and the effectiveness of survey based research. This is the first attempt that the validity of safety culture oversight model has been investigated with empirical data obtained from Korean nuclear power operating organization.

Model quality and safety studies

DEFF Research Database (Denmark)

Petersen, K.E.

1997-01-01

The paper describes the EC initiative on model quality assessment and emphasizes some of the problems encountered in the selection of data from field tests used in the evaluation process. Further, it discusses the impact of model uncertainties in safety studies of industrial plants. The model...... that most of these have never been through a procedure of evaluation, but nonetheless are used to assist in making decisions that may directly affect the safety of the public and the environment. As a major funder of European research on major industrial hazards, DGXII is conscious of the importance......-tain model is appropriate for use in solving a given problem. Further, the findings from the REDIPHEM project related to dense gas dispersion will be highlighted. Finally, the paper will discuss the need for model quality assessment in safety studies....

Safety Challenges and Improvement Strategies of Ethnic Minority Construction Workers: A Case Study in Hong Kong.

Science.gov (United States)

Wu, Chunlin; Luo, Xiaowei; Wang, Tao; Wang, Yue; Sapkota, Bibek

2018-04-18

Due to cultural differences, ethnic minority construction workers are more difficult to manage and more vulnerable to accidents. This study aims to identify the major barriers faced by ethnic minority workers from their own perspectives and determine potential strategies to enhance safety climate of construction projects, thus ultimately improve their safety performance. A survey with modified Nordic safety climate questionnaire was conducted in a certain sub-contractor in Hong Kong. In-depth interviews, status quo description, major challenge investigation and safety knowledge tests were carried as well. The top three most important safety challenges identified are improper stereotypes from the whole industry, lack of opportunities for job assignment, and language barriers. To improve the safety performance, employers should allocate sufficient personal protective equipment and governments should organize unannounced site visits more frequently. Besides, the higher-level management should avoid giving contradictory instructions to foremen against to the standards of supervisors.

Procedure for conducting probabilistic safety assessment: level 1 full power internal event analysis

Energy Technology Data Exchange (ETDEWEB)

Jung, Won Dae; Lee, Y. H.; Hwang, M. J. [and others

2003-07-01

This report provides guidance on conducting a Level I PSA for internal events in NPPs, which is based on the method and procedure that was used in the PSA for the design of Korea Standard Nuclear Plants (KSNPs). Level I PSA is to delineate the accident sequences leading to core damage and to estimate their frequencies. It has been directly used for assessing and modifying the system safety and reliability as a key and base part of PSA. Also, Level I PSA provides insights into design weakness and into ways of preventing core damage, which in most cases is the precursor to accidents leading to major accidents. So Level I PSA has been used as the essential technical bases for risk-informed application in NPPs. The report consists six major procedural steps for Level I PSA; familiarization of plant, initiating event analysis, event tree analysis, system fault tree analysis, reliability data analysis, and accident sequence quantification. The report is intended to assist technical persons performing Level I PSA for NPPs. A particular aim is to promote a standardized framework, terminology and form of documentation for PSAs. On the other hand, this report would be useful for the managers or regulatory persons related to risk-informed regulation, and also for conducting PSA for other industries.

77 FR 27776 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2012-05-11

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

76 FR 18220 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2011-04-01

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

Safety culture in a pharmacy setting using a pharmacy survey on patient safety culture: a cross-sectional study in China.

Science.gov (United States)

Jia, P L; Zhang, L H; Zhang, M M; Zhang, L L; Zhang, C; Qin, S F; Li, X L; Liu, K X

2014-06-30

To explore the attitudes and perceptions of patient safety culture for pharmacy workers in China by using a Pharmacy Survey on Patient Safety Culture (PSOPSC), and to assess the psychometric properties of the translated Chinese language version of the PSOPSC. Cross-sectional study. Data were obtained from 20 hospital pharmacies in the southwest part of China. We performed χ(2) test to explore the differences on pharmacy staff in different hospital and qualification levels and countries towards patient safety culture. We also computed descriptive statistics, internal consistency coefficients and intersubscale correlation analysis, and then conducted an exploratory factor analysis. A test-retest was performed to assess reproducibility of the items. A total of 630 questionnaires were distributed of which 527 were responded to validly (response rate 84%). The positive response rate for each item ranged from 37% to 90%. The positive response rate on three dimensions ('Teamwork', 'Staff Training and Skills' and 'Staffing, Work Pressure and Pace') was higher than that of Agency for Healthcare Research and Quality (AHRQ) data (pculture at different hospital and qualification levels. The internal consistency of the total survey was comparatively satisfied (Cronbach's α=0.89). The results demonstrated that among the pharmacy staffs surveyed in China, there was a positive attitude towards patient safety culture in their organisations. Identifying perspectives of patient safety culture from pharmacists in different hospital and qualification levels are important, since this can help support decisions about action to improve safety culture in pharmacy settings. The Chinese translation of the PSOPSC questionnaire (V.2012) applied in our study is acceptable. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

Fusion reactor safety studies, FY 1977

International Nuclear Information System (INIS)

Darby, J.B. Jr.

1978-04-01

This report reviews the technical progress in the fusion reactor safety studies performed during FY 1977 in the Fusion Power Program at the Argonne National Laboratory. The subjects reported on include safety considerations of the vacuum vessel and first-wall design for the ANL/EPR, the thermal responses of a tokamak reactor first wall, the vacuum wall electrical resistive requirements in relationship to magnet safety, and a major effort is reported on considerations and experiments on air detritiation

Patient Involvement in Patient Safety: A Qualitative Study of Nursing Staff and Patient Perceptions.

Science.gov (United States)

Bishop, Andrea C; Macdonald, Marilyn

2017-06-01

The risk associated with receiving health care has called for an increased focus on the role of patients in helping to improve safety. Recent research has highlighted that patient involvement in patient safety practices may be influenced by patient perceptions of patient safety practices and the perceptions of their health care providers. The objective of this research was to describe patient involvement in patient safety practices by exploring patient and nursing staff perceptions of safety. Qualitative focus groups were conducted with a convenience sample of nursing staff and patients who had previously completed a patient safety survey in 2 tertiary hospital sites in Eastern Canada. Six focus groups (June 2011 to January 2012) were conducted and analyzed using inductive thematic analysis. Four themes were identified: (1) wanting control, (2) feeling connected, (3) encountering roadblocks, and (4) sharing responsibility for safety. Both patient and nursing staff participants highlighted the importance of building a personal connection as a precursor to ensuring that patients are involved in their care and safety. However, perceptions of provider stress and nursing staff workload often reduced the ability of the nursing staff and patient participants to connect with one another and promote involvement. Current strategies aimed at increasing patient awareness of patient safety may not be enough. The findings suggest that providing the context for interaction to occur between nursing staff and patients as well as targeted interventions aimed at increasing patient control may be needed to ensure patient involvement in patient safety.

75 FR 26266 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2010-05-11

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In...) Public Law 92-463. Purpose: The Safety and Occupational Health Study Section will review, discuss, and... cycles pertaining to research issues in occupational safety and health, and allied areas. It is the...

Safety studies conducted on pecan shell fiber, a food ingredient produced from ground pecan shells.

Science.gov (United States)

Dolan, Laurie; Matulka, Ray; Worn, Jeffrey; Nizio, John

2016-01-01

Use of pecan shell fiber in human food is presently limited, but could increase pending demonstration of safety. In a 91-day rat study, pecan shell fiber was administered at dietary concentrations of 0 (control), 50 000, 100 000 or 150 000 ppm. There was no effect of the ingredient on body weight of males or females or food consumption of females. Statistically significant increases in food consumption were observed throughout the study in 100 000 and 150 000 ppm males, resulting in intermittent decreases in food efficiency (150 000 ppm males only) that were not biologically relevant. All animals survived and no adverse clinical signs or functional changes were attributable to the test material. There were no toxicologically relevant changes in hematology, clinical chemistry or urinalysis parameters or organ weights in rats ingesting pecan shell fiber. Any macroscopic or microscopic findings were incidental, of normal variation and/or of minimal magnitude for test substance association. Pecan shell fiber was non-mutagenic in a bacterial reverse mutation test and non-clastogenic in a mouse peripheral blood micronucleus test. Based on these results, pecan shell fiber has an oral subchronic (13-week) no observable adverse effect level (NOAEL) of 150 000 ppm in rats and is not genotoxic at the doses analyzed.

A hybrid simulation approach for integrating safety behavior into construction planning: An earthmoving case study.

Science.gov (United States)

Goh, Yang Miang; Askar Ali, Mohamed Jawad

2016-08-01

One of the key challenges in improving construction safety and health is the management of safety behavior. From a system point of view, workers work unsafely due to system level issues such as poor safety culture, excessive production pressure, inadequate allocation of resources and time and lack of training. These systemic issues should be eradicated or minimized during planning. However, there is a lack of detailed planning tools to help managers assess the impact of their upstream decisions on worker safety behavior. Even though simulation had been used in construction planning, the review conducted in this study showed that construction safety management research had not been exploiting the potential of simulation techniques. Thus, a hybrid simulation framework is proposed to facilitate integration of safety management considerations into construction activity simulation. The hybrid framework consists of discrete event simulation (DES) as the core, but heterogeneous, interactive and intelligent (able to make decisions) agents replace traditional entities and resources. In addition, some of the cognitive processes and physiological aspects of agents are captured using system dynamics (SD) approach. The combination of DES, agent-based simulation (ABS) and SD allows a more "natural" representation of the complex dynamics in construction activities. The proposed hybrid framework was demonstrated using a hypothetical case study. In addition, due to the lack of application of factorial experiment approach in safety management simulation, the case study demonstrated sensitivity analysis and factorial experiment to guide future research. Copyright © 2015 Elsevier Ltd. All rights reserved.

Safety sign designs for children by considering effect of the colors preferences: A case study

Science.gov (United States)

Iftadi, Irwan; Nugraha, Dian Cahya; Jauhari, Wakhid Ahmad

2018-02-01

Color has become a major consideration in ergonomics. Color conveys a message and it is an important element in safety signs. The importance of colors usage in safety sign designs makes the colors research into one of the things that must be done before designing them. So far, research in the related field only focused on the adult's perspective without involving children's perspective in designing the safety signs. This paper aims to find out how children's perception towards colors affects the safety sign designs. This study consist of eight sections which are literature study, direct observation, determining referents and other parameters, determining research respondents, making the booklet, assessing the colors preferences, determining the design's parameter value and creating the safety sign designs. Limitation of the research are the objects are the students with the age of 10 - 11 years old in Grade IV and then the research is conducted in the school day and hours that apply to the school. Chi square test and odds ratio are employed to assess the colors preferences. Twelve safety sign designs are proposed by considering the children's colors perception. The designs are grouped into three types of sign which are Mandatory Action Sign, Warning Sign and Prohibition Sign. Six colors are used to draw the safety signs i.e. red, orange, yellow, green, blue and black. On the basis of the study, it is concluded that the colors that often appears in safety signs is green with the percentage of 75% and that rarely appears is red with the percentage of 8.33%.

Environmental Health and Safety Status of Schools: Case Study in Paveh City of Kermanshah Province

Directory of Open Access Journals (Sweden)

Seyyed Alireza Mousavi

2017-10-01

Full Text Available Background & Aims of the Study: A most part of children time is spent in a school environment. Important part of the basic mission of schools is promoting the health and safety. So assessing the existing conditions is an important factor in promotion and this study conducted to investigate the environmental health and safety status of Paveh city schools in Kermanshah province. Materials & Methods: This is a descriptive-cross sectional study and has performed in Paveh city of Kermanshah province. The study population consisted of primary, secondary and high schools of Paveh city. Data has been collated by referring to schools, direct observation and completion of environmental health and safety checklist. Schools conditions were determined according to the environmental health and safety checklist in desirable, semi-desirable and undesirable. The collected data were analyzed using Excel software, and data means and frequencies sign in tables and were drawn by charts. Results: From the 28 schools have visited 35.6% of school building is old and 63.7% of school building is new built. In the study of all schools in 8% of schools environmental health status were undesirable and in 21% semi-desirable and in 71% were desirable, also safety status in 4% of all schools were undesirable  and in 21% semi-desirable and in 75% were desirable. Undesirable safety conditions related to adjacent to waste accumulation areas, brick buildings without footing beam, inappropriate distance of  first row bench from the boards, lack of green spaces Conclusion: Given the importance of safety in schools, more attention should be paid to this issue. It is essential to compliance with the principles of health and safety in schools, also any consideration and action in this field can be effective in reducing the risk of many related health problems.

Center for Maritime Safety and Health Studies

Data.gov (United States)

Federal Laboratory Consortium — Established in November 2015, the Center for Maritime Safety and Health Studies (CMSHS) promotes safety and health for all maritime workers, including those employed...

A study on a reliability assessment methodology for the VHTR safety systems

International Nuclear Information System (INIS)

Lee, Hyung Sok

2012-02-01

The passive safety system of a 300MWt VHTR (Very High Temperature Reactor)which has attracted worldwide attention recently is actively considered for designing the improvement in the safety of the next generation nuclear power plant. The passive system functionality does not rely on an external source of the electrical support system,but on an intelligent use of the natural phenomena, such as convection, conduction, radiation, and gravity. It is not easy to evaluate quantitatively the reliability of the passive safety for the risk analysis considering the existing active system failure since the classical reliability assessment method could not be applicable. Therefore a new reliability methodology needs to be developed and applied for evaluating the reliability of the conceptual designed VHTR in this study. The preliminary evaluation and conceptualization are performed using the concept of the load and capacity theory related to the reliability physics model. The method of response surface method (RSM) is also utilized for evaluating the maximum temperature of nuclear fuel in this study. The significant variables and their correlation are considered for utilizing the GAMMA+ code. The proposed method might contribute to designing the new passive system of the VHTR

75 FR 56549 - National Institute for Occupational Safety and Health (NIOSH), Safety and Occupational Health...

Science.gov (United States)

2010-09-16

... Suites Hotel, 1900 Diagonal Road, Alexandria, Virginia, 22314, Telephone (703) 684-5900, Fax (703) 684... conduct of Study Section business and for the study section to consider safety and occupational health...

Implementation of Water Safety Plans (WSPs): A Case Study in the Coastal Area in Semarang City, Indonesia

Science.gov (United States)

Budiyono; Ginandjar, P.; Saraswati, L. D.; Pangestuti, D. R.; Martini; Jati, S. P.

2018-02-01

An area of 508.28 hectares in North Semarang is flooded by tidal inundation, including Bandarharjo village, which could affect water quality in the area. People in Bandarharjo use safe water from deep groundwater, without disinfection process. More than 90% of water samples in the Bandaharjo village had poor bacteriological quality. The aimed of the research was to describe the implementation of Water Safety Plans (WSPs) program in Bandarharjo village. This was a descriptive study with steps for implementations adopted the guidelines and tools of the World Health Organization. The steps consist of introducing WSPs program, team building, training the team, examination of water safety before risk assessment, risk assessment, minor repair I, examination of water safety risk, minor repair II (after monitoring). Data were analyzed using descriptive methods. WSPs program has been introduced and formed WSPs team, and the training of the team has been conducted. The team was able to conduct risks assessment, planned the activities, examined water quality, conduct minor repair and monitoring at the source, distribution, and households connection. The WSPs program could be implemented in the coastal area in Semarang, however regularly supervision and some adjustment are needed.

Study on Fusion Safety Infrastructure using ISAM

International Nuclear Information System (INIS)

Oh, Kyemin; Kang, Myungsuk; Heo, Gyunyoung; Kim, Hyoungchan

2013-01-01

The regulation of nuclear facilities have checked and managed safety throughout the entire process from design, construction, operation and decommissioning. Also, the same meaning as the regulatory requirements and design requirements, it will be important indicators for detailed design of K-DEMO. K-DEMO has many uncertainties because it is in conceptual design phase. Also, there is no reference material because demonstration scale fusion power plants were not operated yet in overseas. So, hazard that threaten the integrity of K-DEMO have to be defined preferentially to define regulatory or design requirements. This study proposed method that educe regulatory or design requirements and introduce web-based cloud infrastructure to perform renewal and sharing of information related with safety that is required in the study rapidly as a part of the R and D program funded by National Fusion Research Institute of Korea (NFRI). We have been performing QSR and PIRT in accordance with development of fusion DEMO plant, and preparing OPT, PSA and DPA for regulation requirements. This study introduces our recent research activities about ISAM for fusion and CCI built for expert and extant safety related information. Unlike fission, nuclear fusion's safety goal is non-evacuation of the public during an accident. To satisfy this goal not only various safety issues should be analyzed, but safety objectives, regulatory requirements, and design variables should also be established in detailed design phase. The web-based cloud infrastructure proposed in this paper will be able to offer input data of future studies and, it is expected to contribute on general and technical safety principles for national fusion power plant technology plan

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

Cannabis for the Management of Pain: Assessment of Safety Study (COMPASS).

Science.gov (United States)

Ware, Mark A; Wang, Tongtong; Shapiro, Stan; Collet, Jean-Paul

2015-12-01

Cannabis is widely used as a self-management strategy by patients with a wide range of symptoms and diseases including chronic non-cancer pain. The safety of cannabis use for medical purposes has not been systematically evaluated. We conducted a prospective cohort study to describe safety issues among individuals with chronic non-cancer pain. A standardized herbal cannabis product (12.5% tetrahydrocannabinol) was dispensed to eligible individuals for a 1-year period; controls were individuals with chronic pain from the same clinics who were not cannabis users. The primary outcome consisted of serious adverse events and non-serious adverse events. Secondary safety outcomes included pulmonary and neurocognitive function and standard hematology, biochemistry, renal, liver, and endocrine function. Secondary efficacy parameters included pain and other symptoms, mood, and quality of life. Two hundred and fifteen individuals with chronic pain were recruited to the cannabis group (141 current users and 58 ex-users) and 216 controls (chronic pain but no current cannabis use) from 7 clinics across Canada. The median daily cannabis dose was 2.5 g/d. There was no difference in risk of serious adverse events (adjusted incidence rate ratio = 1.08, 95% confidence interval = .57-2.04) between groups. Medical cannabis users were at increased risk of non-serious adverse events (adjusted incidence rate ratio = 1.73, 95% confidence interval = 1.41-2.13); most were mild to moderate. There were no differences in secondary safety assessments. Quality-controlled herbal cannabis, when used by patients with experience of cannabis use as part of a monitored treatment program over 1 year, appears to have a reasonable safety profile. Longer-term monitoring for functional outcomes is needed. The study was registered with www.controlled-trials.com (ISRCTN19449752). This study evaluated the safety of cannabis use by patients with chronic pain over 1 year. The study found that there was a higher

The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

International Nuclear Information System (INIS)

Shimo, Michikuni

2002-03-01

This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

THE MAIN COMPONENTS OF SAFETY CULTURE IN AVIATION

OpenAIRE

Шостак, Оксана Григорівна; Пришупа, Юлія Юріївна

2012-01-01

The purpose of the article is to summarize, analyse and integrate the numerous reports and studies that have been conducted to define and assess safety culture, as well as the highly related concept of safety climate. This article will enable researchers and safety professionals to better understand and assess safety culture and that it will facilitate the sharing of information and strategies for improving safety culture across organizations and industries.

Safety studies conducted on pecan shell fiber, a food ingredient produced from ground pecan shells

Directory of Open Access Journals (Sweden)

Laurie Dolan

Full Text Available Use of pecan shell fiber in human food is presently limited, but could increase pending demonstration of safety. In a 91-day rat study, pecan shell fiber was administered at dietary concentrations of 0 (control, 50 000, 100 000 or 150 000 ppm. There was no effect of the ingredient on body weight of males or females or food consumption of females. Statistically significant increases in food consumption were observed throughout the study in 100 000 and 150 000 ppm males, resulting in intermittent decreases in food efficiency (150 000 ppm males only that were not biologically relevant. All animals survived and no adverse clinical signs or functional changes were attributable to the test material. There were no toxicologically relevant changes in hematology, clinical chemistry or urinalysis parameters or organ weights in rats ingesting pecan shell fiber. Any macroscopic or microscopic findings were incidental, of normal variation and/or of minimal magnitude for test substance association. Pecan shell fiber was non-mutagenic in a bacterial reverse mutation test and non-clastogenic in a mouse peripheral blood micronucleus test. Based on these results, pecan shell fiber has an oral subchronic (13-week no observable adverse effect level (NOAEL of 150 000 ppm in rats and is not genotoxic at the doses analyzed. Keywords: Pecan shell, Fiber, Rat, Diet, Toxicity, Mutagenicity

Safety, Efficacy and Recurrence rate following tenosynovectomy and ...

African Journals Online (AJOL)

Objective: This study was conducted to compare the safety, efficacy and recurrence rate of primary tenosynovectomy versus intralesional steroid injection in the treatment of sclerosing tenosynovitis of deQuervain. Method: A prospective, comparative study of the safety, efficacy and recurrence rate following intralesional ...

Leadership style and patient safety: implications for nurse managers.

Science.gov (United States)

Merrill, Katreena Collette

2015-06-01

The purpose of this study was to explore the relationship between nurse manager (NM) leadership style and safety climate. Nursing leaders are needed who will change the environment and increase patient safety. Hospital NMs are positioned to impact day-to-day operations. Therefore, it is essential to inform nurse executives regarding the impact of leadership style on patient safety. A descriptive correlational study was conducted in 41 nursing departments across 9 hospitals. The hospital unit safety climate survey and multifactorial leadership questionnaire were completed by 466 staff nurses. Bivariate and regression analyses were conducted to determine how well leadership style predicted safety climate. Transformational leadership style was demonstrated as a positive contributor to safety climate, whereas laissez-faire leadership style was shown to negatively contribute to unit socialization and a culture of blame. Nursing leaders must concentrate on developing transformational leadership skills while also diminishing negative leadership styles.

Systems Analysis of NASA Aviation Safety Program: Final Report

Science.gov (United States)

Jones, Sharon M.; Reveley, Mary S.; Withrow, Colleen A.; Evans, Joni K.; Barr, Lawrence; Leone, Karen

2013-01-01

A three-month study (February to April 2010) of the NASA Aviation Safety (AvSafe) program was conducted. This study comprised three components: (1) a statistical analysis of currently available civilian subsonic aircraft data from the National Transportation Safety Board (NTSB), the Federal Aviation Administration (FAA), and the Aviation Safety Information Analysis and Sharing (ASIAS) system to identify any significant or overlooked aviation safety issues; (2) a high-level qualitative identification of future safety risks, with an assessment of the potential impact of the NASA AvSafe research on the National Airspace System (NAS) based on these risks; and (3) a detailed, top-down analysis of the NASA AvSafe program using an established and peer-reviewed systems analysis methodology. The statistical analysis identified the top aviation "tall poles" based on NTSB accident and FAA incident data from 1997 to 2006. A separate examination of medical helicopter accidents in the United States was also conducted. Multiple external sources were used to develop a compilation of ten "tall poles" in future safety issues/risks. The top-down analysis of the AvSafe was conducted by using a modification of the Gibson methodology. Of the 17 challenging safety issues that were identified, 11 were directly addressed by the AvSafe program research portfolio.

Health, safety, and environmental management system operation in contracting companies: A case study.

Science.gov (United States)

Nassiri, Parvin; Yarahmadi, Rasoul; Gholami, Pari Shafaei; Hamidi, Abdolamir; Mirkazemi, Roksana

2016-05-03

Systematic and cooperative interactions among parent industry and contractors are necessary for a successful health, safety, and environmental management system (HSE-MS). This study was conducted to evaluate the HSE-MS performance in contracting companies in one of the petrochemical industries in Iran during 2013. Managers of parent and contracting companies participated in this study. The data collection forms included 7 elements of an integrated HSE-MS (leadership and commitment; policy and strategic objectives; organization, resources, and documentation; evaluation and risk management; planning; implementation and monitoring; auditing and reviewing). The results showed that mean percentage of the total scores in seven elements of HSE-MS was 85.7% and 87.0% based on self-report and report of parent company, respectively. In conclusion, this study showed that HSE-MS was desirably functioning; however, improvement to ensure health and safety of workers is still required.

Lessons learned from measuring safety culture: an Australian case study.

Science.gov (United States)

Allen, Suellen; Chiarella, Mary; Homer, Caroline S E

2010-10-01

adverse events in maternity care are relatively common but often avoidable. International patient safety strategies advocate measuring safety culture as a strategy to improve patient safety. Evidence suggests it is necessary to fully understand the safety culture of an organisation to make improvements to patient safety. this paper reports a case study examining the safety culture in one maternity service in Australia and considers the benefits of using surveys and interviews to understand safety culture as an approach to identify possible strategies to improve patient safety in this setting. the study took place in one maternity service in two public hospitals in NSW, Australia. Concurrently, both hospitals were undergoing an organisational restructure which was part of a major health reform agenda. The priorities of the reform included improving the quality of care and patient safety; and, creating a more efficient health system by reducing administration inefficiencies and duplication. a descriptive case study using three approaches: the safety culture was identified to warrant improvement across all six safety culture domains. There was reduced infrastructure and capacity to support incident management activities required to improve safety, which was influenced by instability from the organisational restructure. There was a perceived lack of leadership at all levels to drive safety and quality and improving the safety culture was neither a key priority nor was it valued by the organisation. the safety culture was complex as was undertaking this study. We were unable to achieve a desired 60% response rate highlighting the limitations of using safety culture surveys in isolation as a strategy to improve safety culture. Qualitative interviews provided greater insight into the factors influencing the safety culture. The findings of this study provide evidence of the benefits of including qualitative methods with quantitative surveys when examining safety culture

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)

Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition); Realizacion de operaciones en centrales nucleares. Guia de seguridad

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

Phenomenological Studies on Sodium for CSP Applications: A Safety Review

Energy Technology Data Exchange (ETDEWEB)

Armijo, Kenneth Miguel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Concentrating Solar Technologies Dept.; Andraka, Charles E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Concentrating Solar Technologies Dept.

2016-09-01

Sodium as a heat transfer fluid (HTF) can achieve temperatures above 700°C to improve power cycle performance for reducing large infrastructure costs of high-temperature systems. Current concentrating solar power (CSP) sensible HTF’s (e.g. air, salts) have poor thermal conductivity, and thus low heat transfer capabilities, requiring a large receiver. The high thermal conductivity of sodium has demonstrated high heat transfer rates on dish and towers systems, which allow a reduction in receiver area by a factor of two to four, reducing re-radiation and convection losses and cost by a similar factor. Sodium produces saturated vapor at pressures suitable for transport starting at 600°C and reaches one atmosphere at 870°C, providing a wide range of suitable latent operating conditions that match proposed high temperature, isothermal input power cycles. This advantage could increase the receiver and system efficiency while lowering the cost of CSP tower systems. Although there are a number of desirable thermal performance advantages associated with sodium, its propensity to rapidly oxidize presents safety challenges. This investigation presents a literature review that captures historical operations/handling lessons for advanced sodium systems, and the current state-of-knowledge related to sodium combustion behavior. Technical and operational solutions addressing sodium safety and applications in CSP will be discussed, including unique safety hazards and advantages using latent sodium. Operation and maintenance experience from the nuclear industry with sensible and latent systems will also be discussed in the context of safety challenges and risk mitigation solutions.

A comparative study on the effective safety of nuclear technology in Korea

Energy Technology Data Exchange (ETDEWEB)

Soh, Young Jin [Daegu University, Daegu (Korea); Kim, Young Pyoung [Korea University, Seoul (Korea); Jung, Yoon Soo [Myoungji University, Seoul (Korea); Chung, Ik Jae; Choi, Byung Sun [Seoul National University, Seoul (Korea)

2001-12-01

The main purpose of this research is to analyze Korean perception of nuclear risk in comparison with other technological risks. In order to understand the characteristics of risk perception, the concept of 'effective safety' is clarified and defined. This research also covers such issues as relative riskiness of major risks, risk attitude, risk attribution, behavioral pattern for risky situation, and risk knowledge. A nation-wide survey was conducted for this study with a sample size of 1870. It was based on the purposive quota sampling to compare nuclear risk and other technological risks selected are 6 groups of risk; nuclear risk, environmental risk, traffic risk, chemical materials, industrial safety, and other recent risks. Accross these groups, a total of 25 risks are examined. 52 refs., 14 figs., 125 tabs. (Author)

Study on safety educations against individual causal factors of unsafe acts and specification of target trainees

International Nuclear Information System (INIS)

Hirose, Ayako; Takeda, Daisuke

2016-01-01

Many accidents and incidents are caused by unsafe acts. It is important to reduce these unsafe acts for preventing the accidents. The countermeasures for each causal factor behind unsafe acts are needed, however, comparing with improvement of facilities, workers-oriented measures such as safety educations are not sufficient. Then the purposes of this study are as follows: 1) to investigate the individual factors which have great impact of unsafe acts and the existing safety educations which aim to mitigate the impact of these factors, 2) to specify the target trainees to perform these safety educations. To identify common factors that affect unsafe act significantly, a web survey was conducted to 500 workers who have regularly carried out accident prediction training (i.e. Kiken-Yochi training). They were asked the situation which they were apt to act unsafely by free description. As the result, the following three main factors were extracted: impatience, overconfidence, and bothersome. Also, it was found that there were few existing safety educations which aim to mitigate the impact of these factors except for overconfidence. To specify the target trainees to perform safety educations which aim to mitigate the impact of these three factors, another web survey was conducted to 200 personnel in charge of safety at the workplace. They were asked the features of workers who tended to act unsafely by age group. The relationship between the factor that need to mitigate and the trainee who need to receive the education were clarified from the survey. (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.)

Changing patient safety culture in China: a case study of an experimental Chinese hospital from a comparative perspective

Science.gov (United States)

Gu, Yong Hong; Ng, Chui Shan; Cai, Xiao; Xu, Jun; Zhang, Xin Shi; Ke, Dong Ge; Yu, Qian Hui; Chan, Chi Kuen

2018-01-01

Background The World Health Organization highlights that patient safety interventions are not lacking but that the local context affects their successful implementation. Increasing attention is being paid to patient safety in Mainland China, yet few studies focus on patient safety in organizations with mixed cultures. This paper evaluates the current patient safety culture in an experimental Chinese hospital with a Hong Kong hospital management culture, and it aims to explore the application of Hong Kong’s patient safety strategies in the context of Mainland China. Methods A quantitative survey of 307 hospital staff members was conducted using the Hospital Survey on Patient Safety Culture questionnaire. The findings were compared with a similar study on general Chinese hospitals and were appraised with reference to the Manchester Patient Safety Framework. Results Lower scores were observed among participants with the following characteristics: males, doctors, those with more work experience, those with higher education, and those from the general practice and otolaryngology departments. However, the case study hospital achieved better scores in management expectations, actions and support for patient safety, incident reporting and communication, and teamwork within units. Its weaknesses were related to non-punitive responses to errors, teamwork across units, and staffing. Conclusions The case study hospital contributes to a changing patient safety culture in Mainland China, yet its patient safety culture remains mostly bureaucratic. Further efforts could be made to deepen the staff’s patient safety culture mind-set, to realize a “bottom-up” approach to cultural change, to build up a comprehensive and integrated incident management system, and to improve team building and staffing for patient safety. PMID:29750061

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)

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

International Nuclear Information System (INIS)

1987-05-01

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

Angra-1 probabilistic safety study-phase B

International Nuclear Information System (INIS)

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

1988-05-01

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

Behavioral integrity for safety, priority of safety, psychological safety, and patient safety : a team-level study

NARCIS (Netherlands)

Leroy, H.; Dierynck, B.; Anseel, F.; Simons, T.; Halbesleben, J.R.; McCaughey, D.; Savage, G.T.; Sels, L.

2012-01-01

This article clarifies how leader behavioral integrity for safety helps solve follower's double bind between adhering to safety protocols and speaking up about mistakes against protocols. Path modeling of survey data in 54 nursing teams showed that head nurse behavioral integrity for safety

The influence of authentic leadership on safety climate in nursing.

Science.gov (United States)

Dirik, Hasan Fehmi; Seren Intepeler, Seyda

2017-07-01

This study analysed nurses' perceptions of authentic leadership and safety climate and examined the contribution of authentic leadership to the safety climate. It has been suggested and emphasised that authentic leadership should be used as a guidance to ensure quality care and the safety of patients and health-care personnel. This predictive study was conducted with 350 nurses in three Turkish hospitals. The data were collected using the Authentic Leadership Questionnaire and the Safety Climate Survey and analysed using hierarchical regression analysis. The mean authentic leadership perception and the safety climate scores of the nurses were 2.92 and 3.50, respectively. The percentage of problematic responses was found to be less than 10% for only four safety climate items. Hierarchical regression analysis revealed that authentic leadership significantly predicted the safety climate. Procedural and political improvements are required in terms of the safety climate in institutions, where the study was conducted, and authentic leadership increases positive perceptions of safety climate. Exhibiting the characteristics of authentic leadership, or improving them and reflecting them on to personnel can enhance the safety climate. Planning information sharing meetings to raise the personnel's awareness of safety climate and systemic improvements can contribute to creating safe care climates. © 2017 John Wiley & Sons Ltd.

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)

Safety activities in small businesses

Science.gov (United States)

Sinclair, Raymond C.; Cunningham, Thomas R.

2015-01-01

Background Workplace injuries occur at higher rates in smaller firms than in larger firms, and the number of workplace safety activities appear to be inversely associated with those rates. Predictors of safety activities are rarely studied. Methods This study uses data from a national random survey of firms (n = 722) with less than 250 employees conducted in 2002. Results We found that, regardless of firm size or industry, safety activities were more common in 2002 than they were in a similar 1983 study. Having had an OSHA inspection in the last five years and firm size were stronger predictors of safety activities than industry hazardousness and manager’s perceptions of hazardousness. All four variables were significant predictors (β range .19 to .28; R2 = .27). Conclusions Further progress in the prevention of injuries in small firms will require attention to factors likely subsumed within the firm size variable, especially the relative lack of slack resources that might be devoted to safety activities. PMID:26339124

Criticality safety basics, a study guide

Energy Technology Data Exchange (ETDEWEB)

V. L. Putman

1999-09-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

Criticality safety basics, a study guide

International Nuclear Information System (INIS)

Putman, V.L.

1999-01-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates

Feasibility study on floating nuclear power plant (2). Safety design study of FNPP. Contract research

Energy Technology Data Exchange (ETDEWEB)

Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Masao [Niigata Engineering Co. Ltd., Tokyo (Japan); Nakazawa, Toshio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Sato, Kazuo [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

2001-02-01

In the previous report of 'Conceptual Design Study of FNPP (Floating Nuclear Power Plant)', a design study on a concept for FNPP, which is sited off the sea coast on the open sea with water depth of 20m and it is moored on protected sea by the breakwater was conducted and the floating platform guarded by the breakwater was found to be stable enough to install the nuclear power plant from analysis simulating the movement of the platform due to sea wave or wind. In this report, studies on a basic safety design concept of the FNPP, setting natural phenomena for design condition, required safety functions and a review on dynamic analysis of the large floating structure are presented. The studies revealed that the stability of the floating platform is an essential issue for the FNPP soundness, and the design base natural phenomena such as S1 and S2-class storm including S1 and S2-class earthquake should be considered in evaluation of the stability of the floating platform, and it is one of key technical subjects how to set the magnitude of these storm in application of design evaluation on each FNPP case. (J.P.N.)

Field studies of safety security rescue technologies through training and response activities

Science.gov (United States)

Murphy, Robin R.; Stover, Sam

2006-05-01

This paper describes the field-oriented philosophy of the Institute for Safety Security Rescue Technology (iSSRT) and summarizes the activities and lessons learned during calendar year 2005 of its two centers: the Center for Robot-Assisted Search and Rescue and the NSF Safety Security Rescue industry/university cooperative research center. In 2005, iSSRT participated in four responses (La Conchita, CA, Mudslides, Hurricane Dennis, Hurricane Katrina, Hurricane Wilma) and conducted three field experiments (NJTF-1, Camp Hurricane, Richmond, MO). The lessons learned covered mobility, operator control units, wireless communications, and general reliability. The work has collectively identified six emerging issues for future work. Based on these studies, a 10-hour, 1 continuing education unit credit course on rescue robotics has been created and is available. Rescue robots and sensors are available for loan upon request.

Safety certification of airborne software: An empirical study

International Nuclear Information System (INIS)

Dodd, Ian; Habli, Ibrahim

2012-01-01

Many safety-critical aircraft functions are software-enabled. Airborne software must be audited and approved by the aerospace certification authorities prior to deployment. The auditing process is time-consuming, and its outcome is unpredictable, due to the criticality and complex nature of airborne software. To ensure that the engineering of airborne software is systematically regulated and is auditable, certification authorities mandate compliance with safety standards that detail industrial best practice. This paper reviews existing practices in software safety certification. It also explores how software safety audits are performed in the civil aerospace domain. The paper then proposes a statistical method for supporting software safety audits by collecting and analysing data about the software throughout its lifecycle. This method is then empirically evaluated through an industrial case study based on data collected from 9 aerospace projects covering 58 software releases. The results of this case study show that our proposed method can help the certification authorities and the software and safety engineers to gain confidence in the certification readiness of airborne software and predict the likely outcome of the audits. The results also highlight some confidentiality issues concerning the management and retention of sensitive data generated from safety-critical projects.

The Citizenship Safety Project: a pilot study.

Science.gov (United States)

Frederick, K; Barlow, J

2006-02-01

The Government White Paper Saving Lives: Our Healthier Nation (1999) provides a clear indication that accidents are a serious public health problem and have been targeted by the Department of Health as a key area for prevention over the next 10 years. School-based injury prevention programmes have been identified as one of the key settings for the implementation of the White Paper's heath promotion strategies. The Citizen Safety Project (CSP) is a peer-delivered injury prevention programme for Year 10 students (14-15 years) and Year 2 pupils (6-7 years). This paper summarizes the findings of a pilot study that assessed the feasibility of implementing the CSP in schools and of conducting a larger study. Working as part of their Personal Social Health Education lessons, 11 pairs (n = 22) of Year 10 students developed a project to take one accident prevention theme of their choice into a primary school to teach small groups of five or six Year 2 pupils (n = 55). A formative evaluation was conducted, based on interviews with Year 2 and Year 10 teachers (n = 2), and the diaries of Year 10 students. Knowledge of accident prevention and risk awareness was measured in Year 2 pupils using the Draw and Write technique, and impact on Year 10 students was measured using self-esteem and locus of control inventories. Using both statistical and thematic analysis the study concludes that the CSP is well accepted, improves knowledge in Year 2 pupils and boosts confidence in Year 10 students, while concurrently achieving key stage attainment targets. Implications of the study are discussed in terms of future research, as are recommendations with regard to modifications to the project.

A survey of the safety conditions of student housings: A case study in a type one university in Shiraz, Iran

Directory of Open Access Journals (Sweden)

Mehdi Jahangiri

2017-01-01

Full Text Available Objectives: This study aimed to investigate the extent of implementation of safety measures in 14 student housings in one of the largest universities in Fars province, Shiraz, Iran. Method: A cross-sectional study was conducted in 14 student housings of one of the largest universities, located in Shiraz, Iran. Audit checklists were completed and rated thought field inspection and interview. Safety Requirement Index (SRI was then used to evaluate the safety of student housings. SRI was graded on five scales (0-19%: very poor (unsafe; 20-39%: poor (relatively unsafe; 40-59%: moderate; 60-79%: good (relatively safe: and 80-100%: excellent (safe. Results: The mean SRI score was 71.01±15.46%. The highest and lowest level of SRI was 94.11±6.60% for dimensions of public health (and 47.70±18.42% for elevator safety. Conclusion: None of the studied housings was completely safe in all dimensions. Most of the studied housings were categorized as safe in the dimensions of public health and ventilation and air-conditioning systems; relatively safe in the dimensions of electrical, building, fire and kitchen safety; and moderate in the elevator safety and emergency response. Establishment of safety management system is necessary to promote safety in the studied housings. The results of this study indicated the need to inform the authorities about the safety priorities in housings, to promote the safety conditions. The results could also be used to raise awareness regarding their role and responsibilities about the safety of housings.

Quality management of pharmacology and safety pharmacology studies

DEFF Research Database (Denmark)

Spindler, Per; Seiler, Jürg P

2002-01-01

to safety pharmacology studies, and, when indicated, to secondary pharmacodynamic studies, does not influence the scientific standards of studies. However, applying formal GLP standards will ensure the quality, reliability and integrity of studies, which reflect sound study management. It is important...... to encourage a positive attitude among researchers and academics towards these lines, whenever possible. GLP principles applied to the management of non-clinical safety studies are appropriate quality standards when studies are used in the context of protecting public health, and these quality standards...... of pharmacology studies (ICH S7A): primary pharmacodynamic, secondary pharmacodynamic and safety pharmacology studies, and guidance on the quality standards (expectations for GLP conformity) for these study types have been provided. Primary pharmacodynamic studies are the only study types that are fully exempt...

Study on 'Safety qualification of process computers used in safety systems of nuclear power plants'

International Nuclear Information System (INIS)

Bertsche, K.; Hoermann, E.

1991-01-01

The study aims at developing safety standards for hardware and software of computer systems which are increasingly used also for important safety systems in nuclear power plants. The survey of the present state-of-the-art of safety requirements and specifications for safety-relevant systems and, additionally, for process computer systems has been compiled from national and foreign rules. In the Federal Republic of Germany the KTA safety guides and the BMI/BMU safety criteria have to be observed. For the design of future computer-aided systems in nuclear power plants it will be necessary to apply the guidelines in [DIN-880] and [DKE-714] together with [DIN-192]. With the aid of a risk graph the various functions of a system, or of a subsystem, can be evaluated with regard to their significance for safety engineering. (orig./HP) [de

Current collectors for improved safety

Science.gov (United States)

Abdelmalak, Michael Naguib; Allu, Srikanth; Dudney, Nancy J.; Li, Jianlin; Simunovic, Srdjan; Wang, Hsin

2017-12-19

A battery electrode assembly includes a current collector with conduction barrier regions having a conductive state in which electrical conductivity through the conduction barrier region is permitted, and a safety state in which electrical conductivity through the conduction barrier regions is reduced. The conduction barrier regions change from the conductive state to the safety state when the current collector receives a short-threatening event. An electrode material can be connected to the current collector. The conduction barrier regions can define electrical isolation subregions. A battery is also disclosed, and methods for making the electrode assembly, methods for making a battery, and methods for operating a battery.

Radiation safety audit

International Nuclear Information System (INIS)

Kadadunna, K.P.I.K.; Mod Ali, Noriah

2008-01-01

Audit has been seen as one of the effective methods to ensure harmonization in radiation protection. A radiation safety audit is a formal safety performance examination of existing or future work activities by an independent team. Regular audit will assist the management in its mission to maintain the facilities environment that is inherently safe for its employees. The audits review the adequacy of facilities for the type of use, training, and competency of workers, supervision by authorized users, availability of survey instruments, security of radioactive materials, minimization of personnel exposure to radiation, safety equipment, and the required record keeping. All approved areas of use are included in these periodic audits. Any deficiency found in the audit shall be corrected as soon as possible after they are reported. Radiation safety audit is a proactive approach to improve radiation safety practices and identify and prevent any potential radiation accident. It is an excellent tool to identify potential problem to radiation users and to assure that safety measures to eliminate or reduce the problems are fully considered. Radiation safety audit will help to develop safety culture of the facility. It is intended to be the cornerstone of a safety program designed to aid the facility, staff and management in maintaining a safe environment in which activities are carried out. The initiative of this work is to evaluate the need of having a proper audit as one of the mechanism to manage the safety using ionizing radiation. This study is focused on the need of having a proper radiation safety audit to identify deviations and deficiencies of radiation protection programmes. It will be based on studies conducted on several institutes/radiation facilities in Malaysia in 2006. Steps will then be formulated towards strengthening radiation safety through proper audit. This will result in a better working situation and confidence in the radiation protection community

Environmental Regulation and Food Safety: Studies of Protection ...

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

Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Book cover Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Directeur(s) : Veena Jha. Maison(s) d'édition : Edward Elgar, IDRC. 1 janvier 2006. ISBN : 184542512X. 250 pages. e-ISBN : 155250185X.

Gait characteristics in women's safety shoes.

Science.gov (United States)

Goto, Kanako; Abe, Kaoru

2017-11-01

Although workers in Japan are required to wear safety footwear, there is concern about occupational accidents that occur when wearing safety shoes. This study aimed to analyze the effect of wearing hardsoled safety shoes on both spatiotemporal gait characteristics and the muscle activity in the lower extremities. Seventeen young women participated in this study. A 5-m gait trial and a surface electromyography trial were conducted while the women walked in either safety shoes or sports shoes. Paired t-tests were performed to analyze the differences in gait characteristics when walking in the two different pairs of shoes. Walking in safety shoes was associated with a significant increase in vastus lateralis, biceps femoris and tibialis anterior activity. This increased muscle activity in the lower extremities is likely compensating for the lower flexibility of the safety shoes. Copyright © 2017 Elsevier Ltd. All rights reserved.

Revised IAEA Code of Conduct on the Safety and Security of Radioactive Sources

International Nuclear Information System (INIS)

Wheatley, J. S.

2004-01-01

The revised Code of Conduct on the Safety and Security of Radioactive Sources is aimed primarily at Governments, with the objective of achieving and maintaining a high level of safety and security of radioactive sources through the development, harmonization and enforcement of national policies, laws and regulations; and through the fostering of international co-operation. It focuses on sealed radioactive sources and provides guidance on legislation, regulations and the regulatory body, and import/export controls. Nuclear materials (except for sources containing 239Pu), as defined in the Convention on the Physical Protection of Nuclear Materials, are not covered by the revised Code, nor are radioactive sources within military or defence programmes. An earlier version of the Code was published by IAEA in 2001. At that time, agreement was not reached on a number of issues, notably those relating to the creation of comprehensive national registries for radioactive sources, obligations of States exporting radioactive sources, and the possibility of unilateral declarations of support. The need to further consider these and other issues was highlighted by the events of 11th September 2001. Since then, the IAEA's Secretariat has been working closely with Member States and relevant International Organizations to achieve consensus. The text of the revised Code was finalized at a meeting of technical and legal experts in August 2003, and it was submitted to IAEA's Board of Governors for approval in September 2003, with a recommendation that the IAEA General Conference adopt it and encourage its wide implementation. The IAEA General Conference, in September 2003, endorsed the revised Code and urged States to work towards following the guidance contained within it. This paper summarizes the history behind the revised Code, its content and the outcome of the discussions within the IAEA Board of Governors and General Conference. (Author) 8 refs

The role of probabilistic safety assessment and probabilistic safety criteria in nuclear power plant safety

International Nuclear Information System (INIS)

1992-01-01

The purpose of this Safety Report is to provide guidelines on the role of probabilistic safety assessment (PSA) and a range of associated reference points, collectively referred to as probabilistic safety criteria (PSC), in nuclear safety. The application of this Safety Report and the supporting Safety Practice publication should help to ensure that PSA methodology is used appropriately to assess and enhance the safety of nuclear power plants. The guidelines are intended for use by nuclear power plant designers, operators and regulators. While these guidelines have been prepared with nuclear power plants in mind, the principles involved have wide application to other nuclear and non-nuclear facilities. In Section 2 of this Safety Report guidelines are established on the role PSA can play as part of an overall safety assurance programme. Section 3 summarizes guidelines for the conduct of PSAs, and in Section 4 a PSC framework is recommended and guidance is provided for the establishment of PSC values

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

International Nuclear Information System (INIS)

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

1993-10-01

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

A Study on SE Methodology for Design of Big Data Pilot Platform to Improve Nuclear Power Plant Safety

Energy Technology Data Exchange (ETDEWEB)

Shin, Junguk; Cha, Jae-Min; Kim, Jun-Young; Park, Sung-Ho; Yeom, Choong-Sub [Institute for Advanced Engineering (IAE), Yongin (Korea, Republic of)

2016-10-15

A big data concept is expected to have a large impact on the safety of the nuclear power plant (NPP) from the beginning of the big data era. Though there are high interests on the NPP safety with the big data, almost no studies on the logical and physical structures and the systematic design methods of the big data platform for the NPP safety have been conducted. For the current study, a new big data pilot platform for the NPP safety is designed with the main focus on the health monitoring and early warning systems, and a tailored design process based on the systems engineering approaches is proposed to manage inherent high complexity of the platform design. The big data concept is expected to have a large impact on the safety of the NPP. So, in this study, the big data pilot platform for the health monitoring and early warning of the NPP is designed. For this, the development process based on the SE approach for the pilot platform is proposed and the design results along with the proposed process are also presented. Implementation of the individual modules and integrations of those are in currently progress.

A Study on SE Methodology for Design of Big Data Pilot Platform to Improve Nuclear Power Plant Safety

International Nuclear Information System (INIS)

Shin, Junguk; Cha, Jae-Min; Kim, Jun-Young; Park, Sung-Ho; Yeom, Choong-Sub

2016-01-01

A big data concept is expected to have a large impact on the safety of the nuclear power plant (NPP) from the beginning of the big data era. Though there are high interests on the NPP safety with the big data, almost no studies on the logical and physical structures and the systematic design methods of the big data platform for the NPP safety have been conducted. For the current study, a new big data pilot platform for the NPP safety is designed with the main focus on the health monitoring and early warning systems, and a tailored design process based on the systems engineering approaches is proposed to manage inherent high complexity of the platform design. The big data concept is expected to have a large impact on the safety of the NPP. So, in this study, the big data pilot platform for the health monitoring and early warning of the NPP is designed. For this, the development process based on the SE approach for the pilot platform is proposed and the design results along with the proposed process are also presented. Implementation of the individual modules and integrations of those are in currently progress

Safety Awareness & Communications Internship

Science.gov (United States)

Jefferson, Zanani

2015-01-01

The projects that I have worked on during my internships were updating the JSC Safety & Health Action Team JSAT Employee Guidebook, conducting a JSC mishap case study, preparing for JSC Today Close Call success stories, and assisting with event planning and awareness.

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

International Nuclear Information System (INIS)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla

2004-11-01

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

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.

In question: the scientific value of preclinical safety pharmacology and toxicology studies with cell-based therapies

Directory of Open Access Journals (Sweden)

Christiane Broichhausen

2014-01-01

Full Text Available A new cell-based medicinal product containing human regulatory macrophages, known as Mreg_UKR, has been developed and conforms to expectations of a therapeutic drug. Here, Mreg_UKR was subjected to pharmacokinetic, safety pharmacology, and toxicological testing, which identified no adverse reactions. These results would normally be interpreted as evidence of the probable clinical safety of Mreg_UKR; however, we contend that, owing to their uncertain biological relevance, our data do not fully support this conclusion. This leads us to question whether there is adequate scientific justification for preclinical safety testing of similar novel cell-based medicinal products using animal models. In earlier work, two patients were treated with regulatory macrophages prior to kidney transplantation. In our opinion, the absence of acute or chronic adverse effects in these cases is the most convincing available evidence of the likely safety of Mreg_UKR in future recipients. On this basis, we consider that safety information from previous clinical investigations of related cell products should carry greater weight than preclinical data when evaluating the safety profile of novel cell-based medicinal products. By extension, we argue that omitting extensive preclinical safety studies before conducting small-scale exploratory clinical investigations of novel cell-based medicinal products data may be justifiable in some instances.

Code of Conduct on the Safety and Security of Radioactive Sources and the Supplementary Guidance on the Import and Export of Radioactive Sources

International Nuclear Information System (INIS)

2005-01-01

In operative paragraph 4 of its resolution GC(47)/RES/7.B, the General Conference, having welcomed the approval by the Board of Governors of the revised IAEA Code of Conduct on the Safety and Security of Radioactive Sources (GC(47)/9), and while recognizing that the Code is not a legally binding instrument, urged each State to write to the Director General that it fully supports and endorses the IAEA's efforts to enhance the safety and security of radioactive sources and is working toward following the guidance contained in the IAEA Code of Conduct. In operative paragraph 5, the Director General was requested to compile, maintain and publish a list of States that have made such a political commitment. The General Conference, in operative paragraph 6, recognized that this procedure 'is an exceptional one, having no legal force and only intended for information, and therefore does not constitute a precedent applicable to other Codes of Conduct of the Agency or of other bodies belonging to the United Nations system'. In operative paragraph 7 of resolution GC(48)/RES/10.D, the General Conference welcomed the fact that more than 60 States had made political commitments with respect to the Code in line with resolution GC(47)/RES/7.B and encouraged other States to do so. In operative paragraph 8 of resolution GC(48)/RES/10.D, the General Conference further welcomed the approval by the Board of Governors of the Supplementary Guidance on the Import and Export of Radioactive Sources (GC(48)/13), endorsed this Guidance while recognizing that it is not legally binding, noted that more than 30 countries had made clear their intention to work towards effective import and export controls by 31 December 2005, and encouraged States to act in accordance with the Guidance on a harmonized basis and to notify the Director General of their intention to do so as supplementary information to the Code of Conduct, recalling operative paragraph 6 of resolution GC(47)/RES/7.B. 4. The

Contribution of operating feedback to probabilistic safety studies

International Nuclear Information System (INIS)

Guio, J.M. de; Lannoy, A.

1992-03-01

This paper presents the method used for PWR unit operation feedback analysis and its contribution to probabilistic safety studies. The targets were as follows: - use of failure data banks to assess reliability parameters, - use of event data banks to identify and quantify main system initiating events, - determination of a standard operating profile. These studies, performed in the context of nuclear power plant safety programs, prove useful not only to safety engineers but also to equipment experts, designers, operators and maintenance specialists. They constitute basic data for studies in all these areas or the departure point for new investigations. (authors). 3 figs., 3 tabs., 3 refs

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)

Criticality safety studies at VTT Energy

International Nuclear Information System (INIS)

Roine, T.; Anttila, M.

1995-01-01

At VTT Energy a compact reactor physics calculation system is applied in many kind of problems. Generation of group constants for static and dynamic core calculations, flux and dose rate calculations as well as criticality safety studies are performed basically with the same codes. In the presentation a short overview of the wide variety of criticality safety problems analyzed at VTT Energy is given. The calculation system with some illustrative examples is also described. (12 refs., 1 tab.)

Implementation of the safety culture for HANARO Safety Management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which the management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of the safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of safety management in nuclear activities for a reactor application and utilization has also been emphasized more than 10 years in HANARO which is a 30 MW multi-purpose research reactor and achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation like the seminars and lectures related to safety matters, participation in international workshops, the development of safety culture indicators, the survey on the attitude of safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e-Learning program for safety education. (author)

NASA System Safety Handbook. Volume 2: System Safety Concepts, Guidelines, and Implementation Examples

Science.gov (United States)

Dezfuli, Homayoon; Benjamin, Allan; Everett, Christopher; Feather, Martin; Rutledge, Peter; Sen, Dev; Youngblood, Robert

2015-01-01

This is the second of two volumes that collectively comprise the NASA System Safety Handbook. Volume 1 (NASASP-210-580) was prepared for the purpose of presenting the overall framework for System Safety and for providing the general concepts needed to implement the framework. Volume 2 provides guidance for implementing these concepts as an integral part of systems engineering and risk management. This guidance addresses the following functional areas: 1.The development of objectives that collectively define adequate safety for a system, and the safety requirements derived from these objectives that are levied on the system. 2.The conduct of system safety activities, performed to meet the safety requirements, with specific emphasis on the conduct of integrated safety analysis (ISA) as a fundamental means by which systems engineering and risk management decisions are risk-informed. 3.The development of a risk-informed safety case (RISC) at major milestone reviews to argue that the systems safety objectives are satisfied (and therefore that the system is adequately safe). 4.The evaluation of the RISC (including supporting evidence) using a defined set of evaluation criteria, to assess the veracity of the claims made therein in order to support risk acceptance decisions.

EFFECT OF A ROAD SAFETY EDUCATION INTERVENTION ON ROAD SAFETY KNOWLEDGE OF UNIVERSITY DRIVERS IN IBADAN, NIGERIA.

Science.gov (United States)

Olumide, A O; Owoaje, E T

2016-06-01

It is essential for drivers employed in the formal sector to have good knowledge of road safety in order to safeguard their lives and those of the staff they are employed to drive. The study was conducted to determine the effect of a road safety education intervention on road safety knowledge of drivers employed in the University of Ibadan, Nigeria. A quasi-experimental study of 98 intervention and 78 control drivers selected using a cluster sampling technique was conducted. The intervention comprised a two-day training on road safety and first aid. The drivers' knowledge of road safety was measured at baseline, immediately and 4-months post-intervention. Aggregate scores of road safety knowledge were computed giving minimum and maximum obtainable scores of 0 and 16 respectively. Change in mean scores over the three measurement periods was assessed using Repeated Measures Analysis of Variance (ANOVA). Independent t-test was used to compare the scores between intervention and control drivers at each of the assessment periods. Twenty-nine drivers did not complete the study (attrition rate = 16.5%). At baseline, mean road safety knowledge scores for the intervention and control drivers were 12.7±2.2 and 12.9± 2.3 (p = 0.510) respectively. Immediately and four months post intervention, the scores of the intervention drivers were 13.8±1.9 and 12.8±1.6; while scores for the controls were 13.3±2.0 and 13.2±1.8. Repeated measures ANOVA revealed that the increase in knowledge over the three assessment periods was not statistically significant. The intervention resulted in an initial increase in road safety knowledge of the intervention drivers. However, this was not sustained to the forth month post-intervention. This finding suggests periodic refresher trainings to sustain the knowledge acquired.

Seismic safety in conducting large-scale blasts

Science.gov (United States)

Mashukov, I. V.; Chaplygin, V. V.; Domanov, V. P.; Semin, A. A.; Klimkin, M. A.

2017-09-01

In mining enterprises to prepare hard rocks for excavation a drilling and blasting method is used. With the approach of mining operations to settlements the negative effect of large-scale blasts increases. To assess the level of seismic impact of large-scale blasts the scientific staff of Siberian State Industrial University carried out expertise for coal mines and iron ore enterprises. Determination of the magnitude of surface seismic vibrations caused by mass explosions was performed using seismic receivers, an analog-digital converter with recording on a laptop. The registration results of surface seismic vibrations during production of more than 280 large-scale blasts at 17 mining enterprises in 22 settlements are presented. The maximum velocity values of the Earth’s surface vibrations are determined. The safety evaluation of seismic effect was carried out according to the permissible value of vibration velocity. For cases with exceedance of permissible values recommendations were developed to reduce the level of seismic impact.

The German nuclear power plant safety study

International Nuclear Information System (INIS)

1979-01-01

With this study a new approach has been chosen, taking nuclear power plants as an example to assess and to describe the risks arising from the use of modern technology, including those hazards emanating from the rather hypothetical possibility of occurrence of very serious accidents. Following the definition of basic concepts and methods to be applied in risk assessment studied, as well as a brief account of the design and operating mode of nuclear power plants with PWRs', accidents and failures to be considered in a safety study are described. Using the course-of-event and fault tree analysis, the probability of fission product release as a consequence of failures in safety systems or of core meltdown is evaluated. Subsequently, the theoretical model for assessment of reactor accident consequences is presented, discussing such aspects as the dispersion of radioactivity in the atmosphere, the radiation dose model, safety and countermeasures, the model for the evaluation of health hazards as well as methods and calculations for estimating the reliability of risk assessments together with the remaining uncertainties. In an appendix to this study, the analyses presented in the study are discussed in the light of the TMI-2 event. This safety study showing the possibilities of detecting, keeping in check and minimizing harmful effects, can be regarded as a contribution to a better understanding of our modern, highly industrialised society, and eventually to an improvement of the quality of life. (GL) 891 GL/GL 892 MB [de

Safety-Culture Exploration in Taiwan’s Metal Industries: Identifying the Workers’ Background Influence on Safety Climate

Directory of Open Access Journals (Sweden)

Shu-Chiang Lin

2017-10-01

Full Text Available The present study aims to assess the safety-climate level in Taiwan’s metal industries, as well as to identify the influence of workers’ backgrounds on the safety climate. An earlier report showed that a poor safety culture was related to the cause of accidents in Taiwan’s traditional manufacturing industries. This study surveyed a total of 839 workers who voluntarily participated and completed the safety-culture questionnaires. These workers were from a Taiwanese metal company and its five satellite companies. Three safety-climate factors, namely safety perception, safety communication and safety-management systems, were assessed. Confirmatory factor analysis (CFA was conducted by developing structural equation modeling to ensure the questionnaire’s validity. The influence of workers’ backgrounds on the safety climate was identified by using one-way ANOVA. The reliability result of the questionnaire was above the acceptable level. The overall safety-climate score was 4.22 out of a five-point scale for safety perception, 4.23 for safety-management systems and 3.97 for safety communication. The scores indicate a good level of safety climate, with room for improvement in safety communication. Additionally, the influence of workers’ backgrounds on the safety climate was confirmed. Based on the validity test, it was also found that the questionnaire could be improved by reconstructing its questions in its development process in order to increase the safety-climate model’s reliability and validity, as well as its model fit.

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

2004-11-15

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

Design for safety: theoretical framework of the safety aspect of BIM system to determine the safety index

Directory of Open Access Journals (Sweden)

Ai Lin Evelyn Teo

2016-12-01

Full Text Available Despite the safety improvement drive that has been implemented in the construction industry in Singapore for many years, the industry continues to report the highest number of workplace fatalities, compared to other industries. The purpose of this paper is to discuss the theoretical framework of the safety aspect of a proposed BIM System to determine a Safety Index. An online questionnaire survey was conducted to ascertain the current workplace safety and health situation in the construction industry and explore how BIM can be used to improve safety performance in the industry. A safety hazard library was developed based on the main contributors to fatal accidents in the construction industry, determined from the formal records and existing literature, and a series of discussions with representatives from the Workplace Safety and Health Institute (WSH Institute in Singapore. The results from the survey suggested that the majority of the firms have implemented the necessary policies, programmes and procedures on Workplace Safety and Health (WSH practices. However, BIM is still not widely applied or explored beyond the mandatory requirement that building plans should be submitted to the authorities for approval in BIM format. This paper presents a discussion of the safety aspect of the Intelligent Productivity and Safety System (IPASS developed in the study. IPASS is an intelligent system incorporating the buildable design concept, theory on the detection, prevention and control of hazards, and the Construction Safety Audit Scoring System (ConSASS. The system is based on the premise that safety should be considered at the design stage, and BIM can be an effective tool to facilitate the efforts to enhance safety performance. IPASS allows users to analyse and monitor key aspects of the safety performance of the project before the project starts and as the project progresses.

Changing patient safety culture in China: a case study of an experimental Chinese hospital from a comparative perspective

Directory of Open Access Journals (Sweden)

Xu XP

2018-05-01

Full Text Available Xiao Ping Xu,* Dong Ning Deng,* Yong Hong Gu, Chui Shan Ng, Xiao Cai, Jun Xu, Xin Shi Zhang, Dong Ge Ke, Qian Hui Yu, Chi Kuen Chan Clinical Service Department, The University of Hong Kong - Shenzhen Hospital, Shenzhen, Guangdong, People’s Republic of China *These authors contributed equally to this work Background: The World Health Organization highlights that patient safety interventions are not lacking but that the local context affects their successful implementation. Increasing attention is being paid to patient safety in Mainland China, yet few studies focus on patient safety in organizations with mixed cultures. This paper evaluates the current patient safety culture in an experimental Chinese hospital with a Hong Kong hospital management culture, and it aims to explore the application of Hong Kong’s patient safety strategies in the context of Mainland China. Methods: A quantitative survey of 307 hospital staff members was conducted using the Hospital Survey on Patient Safety Culture questionnaire. The findings were compared with a similar study on general Chinese hospitals and were appraised with reference to the Manchester Patient Safety Framework. Results: Lower scores were observed among participants with the following characteristics: males, doctors, those with more work experience, those with higher education, and those from the general practice and otolaryngology departments. However, the case study hospital achieved better scores in management expectations, actions and support for patient safety, incident reporting and communication, and teamwork within units. Its weaknesses were related to non-punitive responses to errors, teamwork across units, and staffing. Conclusions: The case study hospital contributes to a changing patient safety culture in Mainland China, yet its patient safety culture remains mostly bureaucratic. Further efforts could be made to deepen the staff’s patient safety culture mind-set, to realize a �

Sun safety in construction: a U.K. intervention study.

Science.gov (United States)

Houdmont, J; Madgwick, P; Randall, R

2016-01-01

Interventions to promote sun safety in the U.K. construction sector are warranted given the high incidence of skin cancer attributable to sun exposure relative to other occupational groups. To evaluate change in sun safety knowledge and practices among construction workers in response to an educational intervention. A baseline questionnaire was administered, followed by a bespoke sector-specific DVD-based intervention. At 12-month follow-up, participants completed a further questionnaire. Analyses were conducted on a sample of 120 workers (intervention group, n = 70; comparison group, n = 50). At follow-up, the proportion of intervention group participants that reported correct sun safety knowledge was not significantly greater than at baseline. However, the intervention group demonstrated significant positive change on 9 out of 10 behavioural measures, the greatest change being use of a shade/cover when working in the sun followed by regularly checking skin for moles or unusual changes. Exposure to this intervention was linked to some specific positive changes in construction workers' self-reported sun safety practices. These findings highlight the potential for educational interventions to contribute to tackling skin cancer in the UK construction sector. The findings support the development of bespoke educational interventions for other high-risk outdoor worker groups. © The Author 2015. Published by Oxford University Press on behalf of the Society of Occupational Medicine. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Measuring patient safety culture in maternal and child health institutions in China: a qualitative study.

Science.gov (United States)

Wang, Yuanyuan; Liu, Weiwei; Shi, Huifeng; Liu, Chaojie; Wang, Yan

2017-07-12

Patient safety culture (PSC) plays a critical role in ensuring safe and quality care. Extensive PSC studies have been undertaken in hospitals. However, little is known about PSC in maternal and child health (MCH) institutions in China, which provide both population-based preventive services as well as individual care for patients. This study aimed to develop a theoretical framework for conceptualising PSC in MCH institutions in China. The study was undertaken in six MCH institutions (three in Hebei and three in Beijing). Participants (n=118) were recruited through stratified purposive sampling: 20 managers/administrators, 59 care providers and 39 patients. In-depth interviews were conducted with the participants. The interview data were coded using both inductive (based on the existing PSC theory developed by the Agency for Healthcare Research and Quality) and deductive (open coding arising from data) approaches. A PSC framework was formulated through axial coding that connected initial codes and selective coding that extracted a small number of themes. The interviewees considered patient safety in relation to six aspects: safety and security in public spaces, safety of medical services, privacy and information security, financial security, psychological safety and gap in services. A 12-dimensional PSC framework was developed, containing 69 items. While the existing PSC theory was confirmed by this study, some new themes emerged from the data. Patients expressed particular concerns about psychological safety and financial security. Defensive medical practices emerged as a PSC dimension that is associated with not only medical safety but also financial security and psychological safety. Patient engagement was also valued by the interviewees, especially the patients, as part of PSC. Although there are some common features in PSC across different healthcare delivery systems, PSC can also be context specific. In MCH settings in China, the meaning of 'patient safety

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

International Nuclear Information System (INIS)

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

2011-01-01

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

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose

Preliminary study on improving safety culture in Malaysian nuclear industries

International Nuclear Information System (INIS)

Ibrahim, Sabariah Kader; Lee, Y. E.

2012-01-01

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed

Preliminary study on improving safety culture in Malaysian nuclear industries

Energy Technology Data Exchange (ETDEWEB)

Ibrahim, Sabariah Kader [KAIST, Daejeon (Korea, Republic of); Lee, Y. E. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-10-15

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed.

Measuring safety in aviation : empirical results about the relation between safety outcomes and safety management system processes, operational activities and demographic data

NARCIS (Netherlands)

Kaspers, Steffen; Karanikas, Nektarios; Piric, Selma; van Aalst, Robbert; de Boer, Robert Jan; Roelen, Alfred

2017-01-01

A literature review conducted as part of a research project named “Measuring Safety in Aviation – Developing Metrics for Safety Management Systems” revealed several challenges regarding the safety metrics used in aviation. One of the conclusions was that there is limited empirical evidence about the

Plutonium ocean shipment safety between Europe and Japan

International Nuclear Information System (INIS)

Pierce, J.D.; Hohnstreiter, G.F.; McClure, J.D.; Smith, J.D.; Dukart, R.J.; Koski, J.A.; Braithwate, J.W.; Sorenson, N.R.; Yamamoto, K.; Kitamura, T.; Shibata, K.; Ouchi, Y.; Ito, T.

2004-01-01

Sandia National Laboratories (SNL) and Japan Nuclear Cycle Development Institute (JNC) have conducted an extensive emergency response planning study of the safety of the sea transport of plutonium for JNC. This study was conducted in response to international concerns about the safety of the marine transport of PuO2 powder that began with the sea transport of plutonium powder from France to Japan in 1992 using a purposebuilt ship. This emergency response planning study addressed four topics to better define the accident environment for long-range sea transport of nuclear materials. The first topic is a probabilistic safety analysis that evaluates the technical issues of transporting plutonium between Europe and Japan. An engine-room fire aboard a purposebuilt ship is evaluated as the second topic to determine the vulnerability and safety margin of radioactive material packaging for plutonium designed to meet International Atomic Energy Agency (IAEA) standards. The third topic is a corrosion study performed for generic plutonium packaging to estimate the time required to breach the containment boundary in the event of submersion in seawater. The final study topic is a worldwide survey of information on high-value cargo salvage capabilities from sunken ships. The primary purpose of this overall emergency response planning study is to describe and analyze the safety of radioactive material transportation operations for the international transportation of radioactive materials by maritime cargo vessels

Plutonium ocean shipment safety between Europe and Japan

Energy Technology Data Exchange (ETDEWEB)

Pierce, J D; Hohnstreiter, G F; McClure, J D; Smith, J D; Dukart, R J; Koski, J A; Braithwate, J W; Sorenson, N R [Sandia National Labs., Albuquerque, NM (United States); Yamamoto, K; Kitamura, T; Shibata, K; Ouchi, Y; Ito, T [Japan Nuclear Cycle Development Inst., Tokai-mura (Japan)

2004-07-01

Sandia National Laboratories (SNL) and Japan Nuclear Cycle Development Institute (JNC) have conducted an extensive emergency response planning study of the safety of the sea transport of plutonium for JNC. This study was conducted in response to international concerns about the safety of the marine transport of PuO2 powder that began with the sea transport of plutonium powder from France to Japan in 1992 using a purposebuilt ship. This emergency response planning study addressed four topics to better define the accident environment for long-range sea transport of nuclear materials. The first topic is a probabilistic safety analysis that evaluates the technical issues of transporting plutonium between Europe and Japan. An engine-room fire aboard a purposebuilt ship is evaluated as the second topic to determine the vulnerability and safety margin of radioactive material packaging for plutonium designed to meet International Atomic Energy Agency (IAEA) standards. The third topic is a corrosion study performed for generic plutonium packaging to estimate the time required to breach the containment boundary in the event of submersion in seawater. The final study topic is a worldwide survey of information on high-value cargo salvage capabilities from sunken ships. The primary purpose of this overall emergency response planning study is to describe and analyze the safety of radioactive material transportation operations for the international transportation of radioactive materials by maritime cargo vessels.

Spacecraft Fire Safety Demonstration

Data.gov (United States)

National Aeronautics and Space Administration — The objective of the Spacecraft Fire Safety Demonstration project is to develop and conduct large-scale fire safety experiments on an International Space Station...

Initial development of a practical safety audit tool to assess fleet safety management practices.

Science.gov (United States)

Mitchell, Rebecca; Friswell, Rena; Mooren, Lori

2012-07-01

Work-related vehicle crashes are a common cause of occupational injury. Yet, there are few studies that investigate management practices used for light vehicle fleets (i.e. vehicles less than 4.5 tonnes). One of the impediments to obtaining and sharing information on effective fleet safety management is the lack of an evidence-based, standardised measurement tool. This article describes the initial development of an audit tool to assess fleet safety management practices in light vehicle fleets. The audit tool was developed by triangulating information from a review of the literature on fleet safety management practices and from semi-structured interviews with 15 fleet managers and 21 fleet drivers. A preliminary useability assessment was conducted with 5 organisations. The audit tool assesses the management of fleet safety against five core categories: (1) management, systems and processes; (2) monitoring and assessment; (3) employee recruitment, training and education; (4) vehicle technology, selection and maintenance; and (5) vehicle journeys. Each of these core categories has between 1 and 3 sub-categories. Organisations are rated at one of 4 levels on each sub-category. The fleet safety management audit tool is designed to identify the extent to which fleet safety is managed in an organisation against best practice. It is intended that the audit tool be used to conduct audits within an organisation to provide an indicator of progress in managing fleet safety and to consistently benchmark performance against other organisations. Application of the tool by fleet safety researchers is now needed to inform its further development and refinement and to permit psychometric evaluation. Copyright © 2012 Elsevier Ltd. All rights reserved.

Safety assessment of Linum usitatissimum (Linn.) Ingestion in New ...

African Journals Online (AJOL)

Background: The therapeutic safety of herbal medicine is a major concern for consumers and users. After studying the effects of linseed on hair growth in rabbits, the turn is to evaluate its safety by the observation of some clinical, biological and anatomo-pathological aspects. Materials and Methods: A study was conducted ...

On safety management and nuclear safety - A frame of reference for studies of safety management with examples from non-nuclear contects of relevance for nuclear safety

International Nuclear Information System (INIS)

Svenson, O.; Allwin, P.; Salo, I.

2004-03-01

The report includes three case studies of safety management. The studies are presented as chapters, but are written in a format that makes them easy to read separately. Two of the studies cover regulators (the Swedish Civil Aviation Safety Authority, Luftfartsinspektionen) and the Norwegian Petroleum Directorate) and one a regulated activity/industry (a car manufacturer, Volvo Car). The introduction outlines a living system framework and relates this to concepts used in organizational management. The report concludes with some findings with potential relevance for safety management in the nuclear power domain. In the next phase of the work, the regulated counterparts of the regulators here will be investigated in addition to a fourth case study of a regulated activity/industry. (au)

A study of passive safety conditions for fast reactor core

International Nuclear Information System (INIS)

Shimizu, Akinao

1991-01-01

A study has been made for passive safety conditions of fast reactor cores. Objective of the study is to develop a concept of a core with passive safety as well as a simple safety philosophy. A simple safety philosophy, which is wore easy to explain to the public, is needed to enhance the public acceptance for nuclear reactors. The present paper describes a conceptual plan of the study including the definition of the problem a method of approach and identification of tasks to be solved

Study of industry safety management

International Nuclear Information System (INIS)

Park, Pil Su

1987-06-01

This book deals with general remarks, industrial accidents, statistics of industrial accidents, unsafe actions, making machinery and facilities safe, safe activities, having working environment safe, survey of industrial accidents and analysis of causes, system of safety management and operations, safety management planning, safety education, human engineering such as human-machines system, system safety, and costs of disaster losses. It lastly adds individual protective equipment and working clothes including protect equipment for eyes, face, hands, arms and feet.

International Aspects of Nuclear Safety

International Nuclear Information System (INIS)

Lash, T.R.

2000-01-01

Even though not all the world's nations have developed a nuclear power industry, nuclear safety is unquestionably an international issue. Perhaps the most compelling proof is the 1986 accident at Chornobyl nuclear power plant in what is now Ukraine. The U.S. Department of Energy conducts a comprehensive, cooperative effort to reduce risks at Soviet-designed nuclear power plants. In the host countries : Armenia, Ukraine, Russia, Bulgaria, the Czech Republic, Hungary, Lithuania, Slovakia, and Kazakhstan joint projects are correcting major safety deficiencies and establishing nuclear safety infrastructures that will be self-sustaining.The U.S. effort has six primary goals: 1. Operational Safety - Implement the basic elements of operational safety consistent with internationally accepted practices. 2. Training - Improve operator training to internationally accepted standards. 3. Safety Maintenance - Help establish technically effective maintenance programs that can ensure the reliability of safety-related equipment. 4. Safety Systems - Implement safety system improvements consistent with remaining plant lifetimes. 5. Safety Evaluations - Transfer the capability to conduct in-depth plant safety evaluations using internationally accepted methods. 6. Legal and Regulatory Capabilities - Facilitate host-country implementation of necessary laws and regulatory policies consistent with their international treaty obligations governing the safe use of nuclear power

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose

Radiation safety and gynaecological brachytherapy

International Nuclear Information System (INIS)

Crawford, L.

1985-01-01

In 1983, the Radiation Control Section of the South Australian Health Commission conducted an investigation into radiation safety practices in gynaecological brachytherapy. Part of the investigation included a study of the transportation of radioactive sources between hospitals. Several deficiences in radiation safety were found in the way these sources were being transported. New transport regulations came into force in South Australia in July 1984 and since then there have been many changes in the transportation procedure

Patient Safety Culture in Intensive Care Units from the Perspective of Nurses: A Cross-Sectional Study.

Science.gov (United States)

Farzi, Sedigheh; Moladoost, Azam; Bahrami, Masoud; Farzi, Saba; Etminani, Reza

2017-01-01

One of the goals of nursing is providing safe care, prevention of injury, and health promotion of patients. Patient safety in intensive care units is threatened for various reasons. This study aimed to survey patient safety culture from the perspective of nurses in intensive care units. This cross-sectional study was conducted in 2016. Sampling was done using the convenience method. The sample consisted of 367 nurses working in intensive care units of teaching hospitals affiliated to Isfahan University of Medical Sciences. Data collection was performed using a two-part questionnaire that included demographic and hospital survey on Patient Safety Culture (HSOPSC) questionnaire. Data analysis was done using descriptive statistics (mean and standard deviation). Among the 12 dimensions of safety culture, the nurses assigned the highest score to "team work within units" (97.3%) and "Organizational learning-continuous improvement" (84%). They assigned the least score to "handoffs and transitions"(21.1%), "non-punitive response to errors" (24.7%), "Staffing" (35.6%), "Communication openness" (47.5%), and "Teamwork across units" (49.4%). The patient safety culture dimensions have low levels that require adequate attention and essential measures of health care centers including facilitating teamwork, providing adequate staff, and developing a checklist of handoffs and transitions. Furthermore, to increase reporting error and to promote a patient safety culture in intensive care units, some strategies should be adopted including a system-based approach to deal with the error.

The IAEA code of conduct on the safety of radiation sources and the security of radioactive materials. A step forwards or backwards?

International Nuclear Information System (INIS)

Boustany, K.

2001-01-01

About the finalization of the Code of Conduct on the Safety and Security of radioactive Sources, it appeared that two distinct but interrelated subject areas have been identified: the prevention of accidents involving radiation sources and the prevention of theft or any other unauthorized use of radioactive materials. What analysis reveals is rather that there are gaps in both the content of the Code and the processes relating to it. Nevertheless, new standards have been introduced as a result of this exercise and have thus, as an enactment of what constitutes appropriate behaviour in the field of the safety and security of radioactive sources, emerged into the arena of international relations. (N.C.)

Ferrocyanide Safety Project: Subtask 3.4, Aging Studies

International Nuclear Information System (INIS)

Lilga, M.A.; Lumetta, M.R.; Riemath, W.F.; Romine, R.A.; Schiefelbein, G.F.

1992-11-01

The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. This annual report gives the results of the work conducted by PNL in FY 1992 on Subtask 3.4, Aging Studies, which is part of Task 3, Chemical Nature of Feffocyanide in Wastes. Subtask 3.4 deals with the aging behavior and solubilization of ferrocyanide tank waste sludges in a basic aqueous environment. Investigated were the effects of pH variation, ionic strength, salts present in SSTS, and gamma radiation on solubilization of vendor-prepared Na 2 NiFe(CN) 6

Probabilistic studies for a safety assurance program

International Nuclear Information System (INIS)

Iyer, S.S.; Davis, J.F.

1985-01-01

The adequate supply of energy is always a matter of concern for any country. Nuclear power has played, and will continue to play an important role in supplying this energy. However, safety in nuclear power production is a fundamental prerequisite in fulfilling this role. This paper outlines a program to ensure safe operation of a nuclear power plant utilizing the Probabilistic Safety Studies

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)

The Pit and the Safety Pendulum

Energy Technology Data Exchange (ETDEWEB)

Nitschke, Robert Leon; Ramos, Amadeo Gabriel

2000-11-01

The hypothesis of this paper is that the safety analysis pendulum has swung considerably in the direction of increasingly complex and lengthy safety evaluations and intense reviews during the past 30 years. The test of this hypothesis will be a review of the safety analysis conducted for various activities associated with the retrieval of transuranic radioactive waste from burial pits at a National Laboratory site over a span of 30 years. The examination will focus on the safety aspects and the safety analysis that was conducted for the projects. At the conclusion of this examination, the paper will identify five reasons why the changes have taken place.

Proton Conductivity Studies on Biopolymer Electrolytes

International Nuclear Information System (INIS)

Harun, N. I.; Sabri, N. S.; Rosli, N. H. A.; Taib, M. F. M.; Saaid, S. I. Y.; Kudin, T. I. T.; Ali, A. M. M.; Yahya, M. Z. A.

2010-01-01

Proton conducting solid biopolymer electrolyte membranes consisting of methyl cellulose (MC) and different wt.% of ammonium nitrate (NH 4 NO 3 ) were prepared by solution cast technique. Impedance spectroscopy was carried out to study electrical characteristics of bulk materials. The ionic conductivity of the prepared samples was calculated using the bulk resistance (R b ) obtained from impedance spectroscopy plot. The highest ionic conductivity obtained was 1.17x10 -4 Scm -1 for the sample with composition ratio of MC(50): NH 4 NO 3 (50). To enhance the ionic conductivity, propylene carbonate (PC) and ethylene carbonate (EC) plasticizers were introduced. It was found that the ionic conductivity of polymer electrolyte membranes increased with the increase in plasticizers concentration. The ionic conductivities of solid polymer electrolytes based on MC-NH 4 NO 3 -PC was enhanced up to 4.91x10 -3 Scm -1 while for the MC-NH 4 NO 3 -EC system, the highest conductivity was 1.74x10 -2 Scm -1 . The addition of more plasticizer however decreases in mechanical stability of the membranes.

Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to develop the safety evaluation methods and analysis codes needed in the design and construction stage of fast breeder reactor (FBR). In JFY 2012, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination conducted for the reactor establishment permission, development of the analysis codes, such as core damage analysis code, were carried out following the planned schedule. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

Social housing of non-rodents during cardiovascular recordings in safety pharmacology and toxicology studies.

Science.gov (United States)

Prior, Helen; Bottomley, Anna; Champéroux, Pascal; Cordes, Jason; Delpy, Eric; Dybdal, Noel; Edmunds, Nick; Engwall, Mike; Foley, Mike; Hoffmann, Michael; Kaiser, Robert; Meecham, Ken; Milano, Stéphane; Milne, Aileen; Nelson, Rick; Roche, Brian; Valentin, Jean-Pierre; Ward, Gemma; Chapman, Kathryn

2016-01-01

The Safety Pharmacology Society (SPS) and National Centre for the Replacement, Refinement & Reduction of Animals in Research (NC3Rs) conducted a survey and workshop in 2015 to define current industry practices relating to housing of non-rodents during telemetry recordings in safety pharmacology and toxicology studies. The aim was to share experiences, canvas opinion on the study procedures/designs that could be used and explore the barriers to social housing. Thirty-nine sites, either running studies (Sponsors or Contract Research Organisations, CROs) and/or outsourcing work responded to the survey (51% from Europe; 41% from USA). During safety pharmacology studies, 84, 67 and 100% of respondents socially house dogs, minipigs and non-human primates (NHPs) respectively on non-recording days. However, on recording days 20, 20 and 33% of respondents socially house the animals, respectively. The main barriers for social housing were limitations in the recording equipment used, study design and animal temperament/activity. During toxicology studies, 94, 100 and 100% of respondents socially house dogs, minipigs and NHPs respectively on non-recording days. However, on recording days 31, 25 and 50% of respondents socially house the animals, respectively. The main barriers for social housing were risk of damage to and limitations in the recording equipment used, food consumption recording and temperament/activity of the animals. Although the majority of the industry does not yet socially house animals during telemetry recordings in safety pharmacology and toxicology studies, there is support to implement this refinement. Continued discussions, sharing of best practice and data from companies already socially housing, combined with technology improvements and investments in infrastructure are required to maintain the forward momentum of this refinement across the industry. Copyright © 2016 The Authors. Published by Elsevier Inc. All rights reserved.

Irritable bowel syndrome--prognosis and diagnostic safety. A 5-year follow-up study

DEFF Research Database (Denmark)

Svendsen, Jesper Hastrup; Munck, L K; Andersen, J R

1985-01-01

The irritable bowel syndrome is the commonest diagnosis in gastroenterological clinics, although diagnostic criteria and investigatory programs vary. To elucidate the diagnostic safety and prognosis of the syndrome, a retrospective study was conducted. One hundred and twelve consecutive patients...... with irritable bowel syndrome as the final and only abdominal diagnosis in the period 1977-79 were followed up in 1984. Seventeen patients died during the follow-up period; two of these were considered diagnostic failures (chronic pancreatitis and pancreatic cancer). Of the remaining 95 patients, 93 were...

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...

The effects of enforcement and rewards on safety-belt use : a field study in The Netherlands.

NARCIS (Netherlands)

Hagenzieker, M.P.

1990-01-01

It turns out that young male drivers aged between 18 and 25 use their safety belt less often than other driver groups in The Netherlands. For this reason, it was decided to conduct a nationwide campaign to promote safety belt use by military personnel during October and November 1988. The campaign

Nanotechnology Safety Self-Study

Energy Technology Data Exchange (ETDEWEB)

Grogin, Phillip W. [Los Alamos National Laboratory

2016-03-29

Nanoparticles are near-atomic scale structures between 1 and 100 nanometers (one billionth of a meter). Engineered nanoparticles are intentionally created and are used in research and development at Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL). This course, Nanotechnology Safety Self-Study, presents an overview of the hazards, controls, and uncertainties associated with the use of unbound engineered nanoscale particles (UNP) in a laboratory environment.

Patients' and families' perspectives of patient safety at the end of life: a video-reflexive ethnography study.

Science.gov (United States)

Collier, Aileen; Sorensen, Ros; Iedema, Rick

2016-02-01

The aim of this study was to investigate patients' and families' perspectives of safety and quality in the setting of a life-limiting illness. Data reported here were generated from a qualitative study using video-reflexive ethnographic methodology. Data were collected over 18 months and generated through participant observation, shadowing of clinicians, field-interviews and semi-structured interviews with patients and families. The study was conducted at two hospital sites in Sydney, Australia and in patients' homes. Patients with an advanced life-limiting illness (n = 29) ranging in age between 27 and 89 years and family members (n = 5) participated in the study. Patient safety remains important to dying patients and families. For dying people, iatrogenic harm is not regarded as 'one off' incidents. Rather, harm is experienced as a result of an unfolding series of negative events. Critically, iatrogenic harm is emotional, social and spiritual and not solely technical-clinical misadventure and is inextricably linked with feeling unsafe. Thus, patient safety extends beyond narrowly defined technical-clinical parameters to include interpersonal safety. Current approaches to patient safety do not address fully the needs of dying patients and their families. Patients and their families regard poor communication with and by health professionals to be harmful in and of itself. © The Author 2015. Published by Oxford University Press in association with the International Society for Quality in Health Care; all rights reserved.

A Study on the Estimation Method of Risk Based Area for Jetty Safety Monitoring

Directory of Open Access Journals (Sweden)

Byeong-Wook Nam

2015-09-01

Full Text Available Recently, the importance of safety-monitoring systems was highlighted by the unprecedented collision between a ship and a jetty in Yeosu. Accordingly, in this study, we introduce the concept of risk based area and develop a methodology for a jetty safety-monitoring system. By calculating the risk based areas for a ship and a jetty, the risk of collision was evaluated. To calculate the risk based areas, we employed an automatic identification system for the ship, stopping-distance equations, and the regulation velocity near the jetty. In this paper, we suggest a risk calculation method for jetty safety monitoring that can determine the collision probability in real time and predict collisions using the amount of overlap between the two calculated risk based areas. A test was conducted at a jetty control center at GS Caltex, and the effectiveness of the proposed risk calculation method was verified. The method is currently applied to the jetty-monitoring system at GS Caltex in Yeosu for the prevention of collisions.

78 FR 64504 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2013-10-29

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH or..., Number 177, Pages 56235-56236. Contact Person for More Information: Price Connor, Ph.D., NIOSH Health...

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

Flammable Gas Safety Self-Study 52827

Energy Technology Data Exchange (ETDEWEB)

Glass, George [Los Alamos National Laboratory

2016-03-17

This course, Flammable Gas Safety Self-Study (COURSE 52827), presents an overview of the hazards and controls associated with commonly used, compressed flammable gases at Los Alamos National Laboratory (LANL).

Safety analysis procedures for PHWR

International Nuclear Information System (INIS)

Min, Byung Joo; Kim, Hyoung Tae; Yoo, Kun Joong

2004-03-01

The methodology of safety analyses for CANDU reactors in Canada, a vendor country, uses a combination of best-estimate physical models and conservative input parameters so as to minimize the uncertainty of the plant behavior predictions. As using the conservative input parameters, the results of the safety analyses are assured the regulatory requirements such as the public dose, the integrity of fuel and fuel channel, the integrity of containment and reactor structures, etc. However, there is not the comprehensive and systematic procedures for safety analyses for CANDU reactors in Korea. In this regard, the development of the safety analyses procedures for CANDU reactors is being conducted not only to establish the safety analyses system, but also to enhance the quality assurance of the safety assessment. In the first phase of this study, the general procedures of the deterministic safety analyses are developed. The general safety procedures are covered the specification of the initial event, selection of the methodology and accident sequences, computer codes, safety analysis procedures, verification of errors and uncertainties, etc. Finally, These general procedures of the safety analyses are applied to the Large Break Loss Of Coolant Accident (LBLOCA) in Final Safety Analysis Report (FSAR) for Wolsong units 2, 3, 4

Does Employee Safety Matter for Patients Too? Employee Safety Climate and Patient Safety Culture in Health Care.

Science.gov (United States)

Mohr, David C; Eaton, Jennifer Lipkowitz; McPhaul, Kathleen M; Hodgson, Michael J

2015-04-22

We examined relationships between employee safety climate and patient safety culture. Because employee safety may be a precondition for the development of patient safety, we hypothesized that employee safety culture would be strongly and positively related to patient safety culture. An employee safety climate survey was administered in 2010 and assessed employees' views and experiences of safety for employees. The patient safety survey administered in 2011 assessed the safety culture for patients. We performed Pearson correlations and multiple regression analysis to examine the relationships between a composite measure of employee safety with subdimensions of patient safety culture. The regression models controlled for size, geographic characteristics, and teaching affiliation. Analyses were conducted at the group level using data from 132 medical centers. Higher employee safety climate composite scores were positively associated with all 9 patient safety culture measures examined. Standardized multivariate regression coefficients ranged from 0.44 to 0.64. Medical facilities where staff have more positive perceptions of health care workplace safety climate tended to have more positive assessments of patient safety culture. This suggests that patient safety culture and employee safety climate could be mutually reinforcing, such that investments and improvements in one domain positively impacts the other. Further research is needed to better understand the nexus between health care employee and patient safety to generalize and act upon findings.

Diesel oil safety stock in storage and distribution terminals: a case study: Porto Velho/Rio, Brazil

Energy Technology Data Exchange (ETDEWEB)

Freitas, Rubens C. [Agencia Nacional do Petroleo, Gas Natural e Biocombustiveis (ANP), Rio de Janeiro, RJ (Brazil); D' agosto, Marcio A. [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), RJ (Brazil)

2012-07-01

This paper presents a methodology for calculating diesel oil safety stock in distributor terminals located in the northern of Brazil, applied on a case study for terminals in the state of Rondonia. From the mapping of logistic flows related to transport and storage of diesel oil, the risk factors that cause uncertainties in lead time were analyzed and quantified. Through a research conducted among economic agents (producers, distributors and carriers) operating in the region, it was measured the relevance and impact of risk factors on the safety stock in the terminals. The safety stock was calculated by the classical equation of inventories, as well as by the methodology proposed in this paper. The difference between the two methods has unveiled inefficiencies derived from uncertainties in lead time. Recommendations of actions to mitigate the risk factors are included at the end of this paper. (author)

Food safety and organic meats.

Science.gov (United States)

Van Loo, Ellen J; Alali, Walid; Ricke, Steven C

2012-01-01

The organic meat industry in the United States has grown substantially in the past decade in response to consumer demand for nonconventionally produced products. Consumers are often not aware that the United States Department of Agriculture (USDA) organic standards are based only on the methods used for production and processing of the product and not on the product's safety. Food safety hazards associated with organic meats remain unclear because of the limited research conducted to determine the safety of organic meat from farm-to-fork. The objective of this review is to provide an overview of the published results on the microbiological safety of organic meats. In addition, antimicrobial resistance of microbes in organic food animal production is addressed. Determining the food safety risks associated with organic meat production requires systematic longitudinal studies that quantify the risks of microbial and nonmicrobial hazards from farm-to-fork.

A study of leading indicators for occupational health and safety management systems in healthcare.

Science.gov (United States)

Almost, Joan M; VanDenKerkhof, Elizabeth G; Strahlendorf, Peter; Caicco Tett, Louise; Noonan, Joanna; Hayes, Thomas; Van Hulle, Henrietta; Adam, Ryan; Holden, Jeremy; Kent-Hillis, Tracy; McDonald, Mike; Paré, Geneviève C; Lachhar, Karanjit; Silva E Silva, Vanessa

2018-04-23

In Ontario, Canada, approximately $2.5 billion is spent yearly on occupational injuries in the healthcare sector. The healthcare sector has been ranked second highest for lost-time injury rates among 16 Ontario sectors since 2009 with female healthcare workers ranked the highest among all occupations for lost-time claims. There is a great deal of focus in Ontario's occupational health and safety system on compliance and fines, however despite this increased focus, the injury statistics are not significantly improving. One of the keys to changing this trend is the development of a culture of healthy and safe workplaces including the effective utilization of leading indicators within Occupational Health and Safety Management Systems (OHSMSs). In contrast to lagging indicators, which focus on outcomes retrospectively, a leading indicator is associated with proactive activities and consists of selected OHSMSs program elements. Using leading indicators to measure health and safety has been common practice in high-risk industries; however, this shift has not occurred in healthcare. The aim of this project is to conduct a longitudinal study implementing six elements of the Ontario Safety Association for Community and Healthcare (OSACH) system identified as leading indicators and evaluating the effectiveness of this intervention on improving selected health and safety workplace indicators. A quasi-experimental longitudinal research design will be used within two Ontario acute care hospitals. The first phase of the study will focus on assessing current OHSMSs using the leading indicators, determining potential facilitators and barriers to changing current OHSMSs, and identifying the leading indicators that could be added or changed to the existing OHSMS in place. Phase I will conclude with the development of an intervention designed to support optimizing current OHSMSs in participating hospitals based on identified gaps. Phase II will pilot test and evaluate the tailored

Fusion safety program Annual report, Fiscal year 1995

International Nuclear Information System (INIS)

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

1995-12-01

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

Effect of static electronic advertising signs on road safety: an experimental case study.

Science.gov (United States)

Izadpanah, Pedram; Omrani, Reza; Koo, Sheldon; Hadayeghi, Ali

2014-01-01

As technology continues to advance, the outdoor advertising industry is taking advantage of electronic signs, some of which are static electronic signs (SES), with the ability to automatically change the message shown on the sign at regular intervals. Studies indicate that SES has a negative impact on the drivers' visual attention and on vehicle control. However, the actual effects of the SES on the number of collisions have been difficult to prove conclusively. The objective of this article is to generate a clear understanding of the safety impacts of SES on the number collisions by conducting a before-and-after analysis with comparison groups. The analysis was based on a total of 10 SES along the Highway 27 and the Gardiner Expressway of the city of Toronto. The results of the before-and-after study revealed that there was not enough evidence to suggest that these signs have any impact on road safety along the adjacent roadway sections at a 95% confidence interval. The same results were obtained by comparing collisions that occurred during daylight and artificial light.

Program management plan for the conduct of a research, development, and demonstration program for improving the safety of nuclear powerplants

International Nuclear Information System (INIS)

1981-12-01

Congress passed Public Law 96-567, Nuclear Safety Research, Development, and Demonstration Act of 1980, (hereafter referred to as the Act) to provide for an accelerated and coordinated program of light water reactor safety research, development, and demonstration to be carried out by the Department of Energy. In order to assure that this program would be compatible with the needs of Nuclear Regulatory Commission (NRC) and industry, the Department of Energy (DOE) initiated its response to Section 4 of the Act by conducting individual information gathering meetings with NRC and a wide cross section of the nuclear industry. The Department received recommendations on needs of what type of activities would and would not be appropriate for the Department to assist in satisfying these needs. Based on the evaluation of these inputs, it is concluded that the Department's ongoing Light Water Reactor (LWR) safety program is responsive to the Act. Specifically, the Department's ongoing program includes tasks in the areas of regulatory assessment, risk assessment, fission product source term, and emergency preparedness as well as providing technical assistance to the Institute of Nuclear Power Operations (INPO) to improve training of nuclear power personnel. These were among the very high priority efforts that were identified as necessary and appropriate for support by the Department

Patient safety culture in intensive care units from the perspective of nurses: A cross-sectional study

Directory of Open Access Journals (Sweden)

Sedigheh Farzi

2017-01-01

Full Text Available Background: One of the goals of nursing is providing safe care, prevention of injury, and health promotion of patients. Patient safety in intensive care units is threatened for various reasons. This study aimed to survey patient safety culture from the perspective of nurses in intensive care units. Materials and Methods: This cross-sectional study was conducted in 2016. Sampling was done using the convenience method. The sample consisted of 367 nurses working in intensive care units of teaching hospitals affiliated to Isfahan University of Medical Sciences. Data collection was performed using a two-part questionnaire that included demographic and hospital survey on Patient Safety Culture (HSOPSC questionnaire. Data analysis was done using descriptive statistics (mean and standard deviation. Results: Among the 12 dimensions of safety culture, the nurses assigned the highest score to “team work within units” (97.3% and “Organizational learning-continuous improvement” (84%. They assigned the least score to “handoffs and transitions”(21.1%, “non-punitive response to errors” (24.7%, “Staffing” (35.6%, “Communication openness” (47.5%, and “Teamwork across units” (49.4%. Conclusions: The patient safety culture dimensions have low levels that require adequate attention and essential measures of health care centers including facilitating teamwork, providing adequate staff, and developing a checklist of handoffs and transitions. Furthermore, to increase reporting error and to promote a patient safety culture in intensive care units, some strategies should be adopted including a system-based approach to deal with the error.

Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

Science.gov (United States)

Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

2013-12-01

This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

Safety analysis and related studies

International Nuclear Information System (INIS)

Lelievre, J.

1979-12-01

Several examples of reactor safety studies are given. For light water reactors, the consequences of loss of coolant, the disposition of the fuel elements and the behaviour under irradiation of the steels used for containment are described. For fast reactors, the disposition of fuel elements in the case of cooling accidents and sodium fies are described. Examples given of studies not specific to a particular reactor type include studies of non-destructive testing and those of reliability

Use of safety management practices for improving project performance.

Science.gov (United States)

Cheng, Eddie W L; Kelly, Stephen; Ryan, Neal

2015-01-01

Although site safety has long been a key research topic in the construction field, there is a lack of literature studying safety management practices (SMPs). The current research, therefore, aims to test the effect of SMPs on project performance. An empirical study was conducted in Hong Kong and the data collected were analysed with multiple regression analysis. Results suggest that 3 of the 15 SMPs, which were 'safety committee at project/site level', 'written safety policy', and 'safety training scheme' explained the variance in project performance significantly. Discussion about the impact of these three SMPs on construction was provided. Assuring safe construction should be an integral part of a construction project plan.

The Safety Case and Safety Assessment for the Disposal of Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-15

This Safety Guide provides guidance and recommendations on meeting the safety requirements in respect of the safety case and supporting safety assessment for the disposal of radioactive waste. The safety case and supporting safety assessment provide the basis for demonstration of safety and for licensing of radioactive waste disposal facilities and assist and guide decisions on siting, design and operations. The safety case is also the main basis on which dialogue with interested parties is conducted and on which confidence in the safety of the disposal facility is developed. This Safety Guide is relevant for operating organizations preparing the safety case as well as for the regulatory body responsible for developing the regulations and regulatory guidance that determine the basis and scope of the safety case. Contents: 1. Introduction; 2. Demonstrating the safety of radioactive waste disposal; 3. Safety principles and safety requirements; 4. The safety case for disposal of radioactive waste; 5. Radiological impact assessment for the period after closure; 6. Specific issues; 7. Documentation and use of the safety case; 8. Regulatory review process.

Health, safety and environmental unit performance assessment model under uncertainty (case study: steel industry).

Science.gov (United States)

Shamaii, Azin; Omidvari, Manouchehr; Lotfi, Farhad Hosseinzadeh

2017-01-01

Performance assessment is a critical objective of management systems. As a result of the non-deterministic and qualitative nature of performance indicators, assessments are likely to be influenced by evaluators' personal judgments. Furthermore, in developing countries, performance assessments by the Health, Safety and Environment (HSE) department are based solely on the number of accidents. A questionnaire is used to conduct the study in one of the largest steel production companies in Iran. With respect to health, safety, and environment, the results revealed that control of disease, fire hazards, and air pollution are of paramount importance, with coefficients of 0.057, 0.062, and 0.054, respectively. Furthermore, health and environment indicators were found to be the most common causes of poor performance. Finally, it was shown that HSE management systems can affect the majority of performance safety indicators in the short run, whereas health and environment indicators require longer periods of time. The objective of this study is to present an HSE-MS unit performance assessment model in steel industries. Moreover, we seek to answer the following question: what are the factors that affect HSE unit system in the steel industry? Also, for each factor, the extent of impact on the performance of the HSE management system in the organization is determined.

Codifying knowledge to improve patient safety: a qualitative study of practice-based interventions.

Science.gov (United States)

Turner, Simon; Higginson, Juliet; Oborne, C Alice; Thomas, Rebecca E; Ramsay, Angus I G; Fulop, Naomi J

2014-07-01

Although it is well established that health care professionals use tacit and codified knowledge to provide front-line care, less is known about how these two forms of knowledge can be combined to support improvement related to patient safety. Patient safety interventions involving the codification of knowledge were co-designed by university and hospital-based staff in two English National Health Service (NHS) hospitals to support the governance of medication safety and mortality and morbidity (M&M) meetings. At hospital A, a structured mortality review process was introduced into three clinical specialities from January to December 2010. A qualitative approach of observing M&M meetings (n = 30) and conducting interviews (n = 40) was used to examine the impact on meetings and on front-line clinicians and hospital managers. At hospital B, a medication safety 'scorecard' was administered on a general medicine and elderly care ward from September to November 2011. Weekly feedback meetings were observed (n = 18) and interviews with front-line staff conducted (n = 10) to examine how knowledge codification influenced behaviour. Codification was shown to support learning related to patient safety at the micro (front-line service) level by structuring the sharing of tacit knowledge, but the presence of professional and managerial boundaries at the organisational level affected the codification initiatives' implementation. The findings suggest that codifying knowledge to support improvement presents distinct challenges at the group and organisational level; translating knowledge across these levels is contingent on the presence of enabling organisational factors, including the alignment of learning from clinical practice with its governance. Copyright © 2014 The Authors. Published by Elsevier Ltd.. All rights reserved.

The advanced neutron source facility: Safety philosophy and studies

International Nuclear Information System (INIS)

Greene, S.R.; Harrington, R.M.

1988-01-01

The Advanced Neutron Source (ANS) is currently the only new civilian nuclear reactor facility proposed for construction in the United States. Even though the thermal power of this research-oriented reactor is a relatively low 300 MW, the design will undoubtedly receive intense scrutiny before construction is allowed to proceed. Safety studies are already under way to ensure that the maximum degree of safety in incorporated into the design and that the design is acceptable to the Department of Energy (DOE) and can meet the Nuclear Regulatory Commission regulations. This document discusses these safety studies

Patient safety: Safety culture and patient safety ethics

DEFF Research Database (Denmark)

Madsen, Marlene Dyrløv

2006-01-01

,demonstrating significant, consistent and sometimes large differences in terms of safety culture factors across the units participating in the survey. Paper 5 is the results of a study of the relation between safety culture, occupational health andpatient safety using a safety culture questionnaire survey......Patient safety - the prevention of medical error and adverse events - and the initiative of developing safety cultures to assure patients from harm have become one of the central concerns in quality improvement in healthcare both nationally andinternationally. This subject raises numerous...... challenging issues of systemic, organisational, cultural and ethical relevance, which this dissertation seeks to address through the application of different disciplinary approaches. The main focus of researchis safety culture; through empirical and theoretical studies to comprehend the phenomenon, address...

Bioequivalence study of two losartan tablet formulations with special emphasis on cardiac safety.

Science.gov (United States)

Khandave, Suhas S; Sawant, Satish V; Sahane, Rakhi V; Murthi, Vivekanand; Dhanure, Shivanand S; Surve, Pradeep G

2012-05-01

To study the bioequivalence of Losartan Potassium Tablets 50 mg manufactured by Micro Labs Ltd. India to Cozaar® Tablets 50 mg, manufactured by Merck Sharp and Dohme Ltd., UK in normal healthy adult subjects under fasting condition along with the comparative safety evaluation of both treatments. The in vitro dissolution studies were carried out on 12 units each of test and reference products using the paddle method and dissolution media like water, 0.1 N hydrochloric acid with pH 1.2, pH 4.5 acetate buffer and pH 6.8 phosphate buffer. An open label, randomized, two-treatment, two-period, two-sequence, crossover bioequivalence study with a washout period of 7 days was conducted in 60 healthy Indian male subjects. Serial blood samples were collected after drug administration in each study period. Plasma concentrations of losartan and losartan acid were determined using a validated LC-MS-MS method. The pharmacokinetic parameters of losartan and losartan acid were determined using a non compartmental model. Occurrence of adverse events, change in systolic blood pressure, diastolic blood pressure, heart rate and QT interval from the baseline to 3.50 h post dose were studied and compared between the two treatments as safety parameters. The in vitro study proved the essential similarity of both the formulations as evident from the similarity factor of > 50% in all the dissolution media. The ratios for geometric least square means and 90% confidence intervals were within the acceptance criteria of 80% to 125% for log transformed C(max), AUC(0-t) and AUC(0-∞) for losartan. No statistically significant difference between the two treatments was observed for either of the safety parameters. The test product Losartan Potassium tablets 50 mg manufactured by Micro Labs Limited, India was bioequivalent to Cozaar® tablets 50 mg, manufactured by Merck Sharp and Dohme Ltd., UK in terms of rate and extent of absorption. Both treatments were well tolerated and had similar non

Development and validation of a new safety climate scale for petrochemical industries.

Science.gov (United States)

Jafari, Mohammad Javad; Eskandari, Davood; Valipour, Firouz; Mehrabi, Yadollah; Charkhand, Hossein; Mirghotbi, Mostafa

2017-01-01

While a considerable body of research has studied safety climate and its role as a leading indicator of organizational safety, much of this work has been conducted with Western manufacturing samples. The current study puts emphasis on the cross-validation of a safety climate model in the non-Western industrial context of Iranian petrochemical industries. The current study was performed in one petrochemical company in Iran. The scale was developed through conducting a literature review followed by a qualitative study with expert participation. After performing a screening process, the initial number of items on the scale was reduced to 68. Ten dimensions (including management commitment, workers' empowerment, communication, blame culture, safety training, job satisfaction, interpersonal relationship, supervision, continuous improvement, and reward system) together with 37 items were extracted from the exploratory factor analysis (EFA) to measure safety climate. Acceptable ranges of internal consistency statistics for the sub-scales were observed. Confirmatory factor analysis (CFA) confirmed the construct validity of the developed safety climate scale for the petrochemical industry workers. The results of reliability showed that the Cronbach's alpha coefficient for the designed scale was 0.94. The ICC was obtained 0.92. This study created a valid and reliable scale for measuring safety climate in petrochemical industries.

An observational study of road safety around selected primary schools in Ibadan municipality, Oyo State, Southwestern Nigeria.

Science.gov (United States)

Sangowawa, Adesola O; Adebiyi, Akindele O; Faseru, Babalola; Popoola, Olusola J

2012-01-01

Child pedestrians have been identified as vulnerable road users. Although walking as a means of transport has health and other benefits, it exposes children to the risk of road traffic injuries. This study was conducted to assess the availability of road safety features around government-owned primary schools in Ibadan municipality. A multistage sampling technique was used to select 46 of the 74 schools in the study area. Some (11) of the selected schools were sited within the same premises and shared a common entrance; thus a total of 35 school premises were eventually observed. Trained research assistants observed the school environment around the selected schools for road safety features such as location of schools, presence of "school", "child crossing" and "speed limit" road signs, and presence of traffic calming devices (road bumps or zebra crossing). Five (14%) of the schools were located on major roads and eight (23%) had road signs indicating that a school was nearby. Seven (20%) had road bumps close to the school, 15 (43%) had a warden who assisted children to cross, and none had a zebra crossing. Five (14%) schools had pedestrian sidewalks. The study revealed that the environment around a number of the observed schools in the municipality compromised the pupils' road safety. The local government, school authorities, parents, and road safety professionals need to institute definite measures to enhance the road safety environment around schools in the municipality.

Preliminary Study on the Revision of Nuclear Safety Policy Statement

International Nuclear Information System (INIS)

Lee, Y. E.; Lee, S. H.; Chang, H. S.; Choi, K. S.; Jung, S. J.

2011-01-01

Nuclear safety policy in Korea is currently declared in the Nuclear Safety Charter as the highest tier document and safety principles and directions are announced in the Nuclear Safety Policy Statement. As the circumstances affecting on the nuclear safety policy change, it needs to revise the Statement. This study aims to develop the revised Nuclear Safety Policy Statement to declare that securing safety is a prerequisite to the utilization of nuclear energy, and that all workers in nuclear industry and regulatory body must adhere to the principle of priority to safety. As a result, two different types of revision are being prepared as of August. One is based on the spirit of Nuclear Safety Charter as well as the direction of future-oriented safety policies including the changes in the environment after declaration of the Statement. The other is to declare the fundamental safety objective and safety principles as the top philosophy of national nuclear safety policy by adopting the '10 Safety Principles in IAEA Safety Fundamental' instead of the current Charter. Both versions of revision are subject to further in-depth discussion. However once the revision is finalized and declared, it would be useful to accomplish effectively the organizational responsibilities and to enhance the public confidence in nuclear safety by performing the regulatory activities in a planned and systematic manner and promulgating the government's dedication to priority to safety

Keeping nurse researchers safe: workplace health and safety issues.

Science.gov (United States)

Barr, Jennieffer; Welch, Anthony

2012-07-01

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

Progress in the development of methodology for fusion safety systems studies

International Nuclear Information System (INIS)

Ho, S.K.; Cambi, G.; Ciattaglia, S.; Fujii-e, Y.; Seki, Y.

1994-01-01

The development of fusion safety systems-study methodology, including the aspects of schematic classification of overall fusion safety system, qualitative assessment of fusion system for identification of critical accident scenarios, quantitative analysis of accident consequences and risk for safety design evaluation, and system-level analysis of accident consequences and risk for design optimization, by a consortium of international efforts is presented. The potential application of this methodology into reactor design studies will facilitate the systematic assessment of safety performance of reactor designs and enhance the impacts of safety considerations on the selection of design configurations

Project safety studies - nuclear waste management (PSE)

International Nuclear Information System (INIS)

1981-10-01

The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

Observational Studies on Evaluating the Safety and Adverse Effects of Traditional Chinese Medicine

Directory of Open Access Journals (Sweden)

Jung-Nein Lai

2013-01-01

Full Text Available Background. This study aims to share our experiences when carrying out observational studies of traditional Chinese medicine (TCM. Methods. We have proactively monitored the safety profiles of Duhuo Jisheng Tang (DJT, Suan Zao Ren Tang (SZRT, and TMN-1. A list of adverse events (AEs, complete blood counts, and liver and kidney function tests were obtained from the participants during their scheduled hospital visits. Retrospective observational studies were conducted based on the reimbursement database of the National Health Insurance system, Taiwan, to explore the relationship between the use of TCM that have been adulterated by aristolochic acid and the risk from both nephrotoxins and carcinogens. Results. A total of 221, 287, and 203 AEs were detected after SZRT, DJT, and TMN-1 had been taken, respectively. Dizziness, headache, stomach ache, and diarrhea were judged to be probably related to SZRT treatment. Retrospective observational studies found an association between the consumption of aristolochic acid-containing Chinese formulae such as Mu Tong and an increased risk of CKD, ESRD, and urinary tract cancer. Conclusion. Prospective and retrospective observational studies seem to have specific advantages when investigating the safety and adverse effects of TCM therapies, as well as possibly other alternative/complementary therapies.

Observational Studies on Evaluating the Safety and Adverse Effects of Traditional Chinese Medicine

Science.gov (United States)

Tang, Jin-Ling; Wang, Jung-Der

2013-01-01

Background. This study aims to share our experiences when carrying out observational studies of traditional Chinese medicine (TCM). Methods. We have proactively monitored the safety profiles of Duhuo Jisheng Tang (DJT), Suan Zao Ren Tang (SZRT), and TMN-1. A list of adverse events (AEs), complete blood counts, and liver and kidney function tests were obtained from the participants during their scheduled hospital visits. Retrospective observational studies were conducted based on the reimbursement database of the National Health Insurance system, Taiwan, to explore the relationship between the use of TCM that have been adulterated by aristolochic acid and the risk from both nephrotoxins and carcinogens. Results. A total of 221, 287, and 203 AEs were detected after SZRT, DJT, and TMN-1 had been taken, respectively. Dizziness, headache, stomach ache, and diarrhea were judged to be probably related to SZRT treatment. Retrospective observational studies found an association between the consumption of aristolochic acid-containing Chinese formulae such as Mu Tong and an increased risk of CKD, ESRD, and urinary tract cancer. Conclusion. Prospective and retrospective observational studies seem to have specific advantages when investigating the safety and adverse effects of TCM therapies, as well as possibly other alternative/complementary therapies. PMID:24159351

Industrial Student Apprenticeship: Understanding Health and Safety

Science.gov (United States)

Simanjuntak, M. V.; Abdullah, A. G.; Puspita, R. H.; Mahdan, D.; Kamaludin, M.

2018-02-01

The level of accident in industry is very high caused by lack of knowledge and awareness of workers toward the health and safety. Health and Safety are efforts to create a comfortable and productive atmosphere to accomplish a purpose or goal as maximum risk in the workplace. Vocational Education students must conduct training on business and industry, prior to that they should have a clear understanding on occupational health and safety. The purpose of this research is to analyze the understanding, preparation, and implementation of work health and safety of the students. Method used is descriptive method and data are collected using instrument, observation and interview. The result of study is conclusion of understanding occupational health and safety of vocational education students.

Safety cost management in construction companies: A proposal classification.

Science.gov (United States)

López-Alonso, M; Ibarrondo-Dávila, M P; Rubio, M C

2016-06-16

Estimating health and safety costs in the construction industry presents various difficulties, including the complexity of cost allocation, the inadequacy of data available to managers and the absence of an accounting model designed specifically for safety cost management. Very often, the costs arising from accidents in the workplace are not fully identifiable due to the hidden costs involved. This paper reviews some studies of occupational health and safety cost management and proposes a means of classifying these costs. We conducted an empirical study in which the health and safety costs of 40 construction worksites are estimated. A new classification of the health and safety cost and its categories is proposed: Safety and non-safety costs. The costs of the company's health and safety policy should be included in the information provided by the accounting system, as a starting point for analysis and control. From this perspective, a classification of health and safety costs and its categories is put forward.

A study on optimization of the nuclear safety system

International Nuclear Information System (INIS)

Lee, Sang Hoon; Koh, Byung Joon; Kim, Jin Soo; Kim, Byoung Do; Cho, Seong Won; Kwon, Seog Kwon; Choi, Kwang Sik

1986-12-01

The number of nuclear facilities (nuclear power plants, research reactors, nuclear fuel facilities) under construction or in operation in Korea continues to increase and this has brought about increased importance and concerns toward nuclear safety in Korea. Also, domestic nuclear related organizations are increasingly carrying out the design/construction of nuclear power plants and the development /supply of nuclear fuels. In order to flexibly respond to these changes and to suggest direction to take, it is necessary to re-examine the current nuclear safety regulation system. This study is carried out in two stages and this report describes the results of the analysis and the assessment of the nuclear licencing system of such foreign countries as sweden and German, as the first of the two. In this regard, this study includes the analysis on the backgrounds on the choice of nuclear licensing system, the analysis on the licensing procedures, the analysis on the safety inspection system and the enforcement laws, the analysis on the structure and function of the regulatory, business and research organizations as well as the analysis on the relationship between the safety research and the regulatory duties. In this study, the German safety inspection system and the enforcement procedures and the Swedish nuclear licensing system are analyzed in detail. By comparing and assessing the finding with the current Korea Nuclear Licensing System, this study points out some reform measures of the Korean system that needs to improved. With the changing situations in mind, this study aims to develop the nuclear safety regulation system optimized for Korean situation by re-examining the current regulation system. (Author)

The Role of Hospital Inpatients in Supporting Medication Safety: A Qualitative Study.

Directory of Open Access Journals (Sweden)

Sara Garfield

Full Text Available Inpatient medication errors are a significant concern. An approach not yet widely studied is to facilitate greater involvement of inpatients with their medication. At the same time, electronic prescribing is becoming increasingly prevalent in the hospital setting. In this study we aimed to explore hospital inpatients' involvement with medication safety-related behaviours, facilitators and barriers to this involvement, and the impact of electronic prescribing.We conducted ethnographic observations and interviews in two UK hospital organisations, one with established electronic prescribing and one that changed from paper to electronic prescribing during our study. Researchers and lay volunteers observed nurses' medication administration rounds, pharmacists' ward rounds, doctor-led ward rounds and drug history taking. We also conducted interviews with healthcare professionals, patients and carers. Interviews were audio-recorded and transcribed. Observation notes and transcripts were coded thematically.Paper or electronic medication records were shown to patients in only 4 (2% of 247 cases. However, where they were available during patient-healthcare professional interactions, healthcare professionals often viewed them in order to inform patients about their medicines and answer any questions. Interprofessional discussions about medicines seemed more likely to happen in front of the patient where paper or electronic drug charts were available near the bedside. Patients and carers had more access to paper-based drug charts than electronic equivalents. However, interviews and observations suggest there are potentially more significant factors that affect patient involvement with their inpatient medication. These include patient and healthcare professional beliefs concerning patient involvement, the way in which healthcare professionals operate as a team, and the underlying culture.Patients appear to have more access to paper-based records than

Safety and effectiveness of the Vibrant Soundbridge in treating conductive and mixed hearing loss: A systematic review.

Science.gov (United States)

Ernst, Arne; Todt, Ingo; Wagner, Jan

2016-06-01

For many years, the therapeutic approach for conductive and/or mixed hearing loss has consisted of middle ear surgery with replacement of defect ossicles, and if possible the application of a hearing aid. Advances in technology have led to the introduction of electronmagnetic active implantable devices such as the Vibrant Soundbridge (VSB). With its various coupling techniques for different pathophysiological situations in the middle ear, the VSB offers greater improvement in the hearing performance of affected persons. PubMed, OvidSP (MEDLINE), EMBASE (DIMDI), the National Institue for Health research (NIHR) Centre for Reviews and Dissemination (including the National Health Service Economic Evaluation Database, Database of Abstracts of Reviews of Effects, and Health Technology Assessment), and the Cochrane Library were searched to identify articles published between January 2006 and April 2014 that evaluated the safety and effectiveness of the VSB in comparison to no intervention, bone conduction hearing implants (BCHI), and middle ear surgery plus hearing aids for adults and children with conductive or mixed hearing loss. Study selection and data extraction was carried out by multiple reviewers. Study quality was assessed using the Oxford Centre for Evidence-Based Medicine levels of evidence (2011); and a checklist available from the Evidence Analysis Library, Academy of Nutrition and Diabetics. Thirty-six publications were identified: 19 on VSB outcomes in 294 individuals, 13 on BCHI outcomes in 666 individuals, and four on middle ear surgery plus hearing aid outcomes in 43 individuals. Two systematic reviews were also identified. Heterogeneous outcome measures made it difficult to summarize data. In general, the VSB proved to be safe and effective when compared to no intervention and BCHI, and provided more and consistent hearing gain compared to middle ear surgery plus conventional hearing aids. As demonstrated in the literature, the VSB as an active device

Occupational health and safety issues in Ontario sawmills and veneer/plywood plants: a pilot study.

Science.gov (United States)

Verma, Dave K; Demers, Cecil; Shaw, Don; Verma, Paul; Kurtz, Lawrence; Finkelstein, Murray; des Tombe, Karen; Welton, Tom

2010-01-01

A pilot study was conducted within the Ontario sawmill and veneer/plywood manufacturing industry. Information was collected by postal questionnaire and observational walk-through surveys. Industrial hygiene walk-through surveys were conducted at 22 work sites, and measurements for wood dust, noise, and bioaerosol were taken. The aim of the study was to obtain data on the current status regarding health and safety characteristics and an estimate of wood dust, noise, and bioaerosol exposures. The occupational exposure to wood dust and noise are similar to what has been reported in this industry in Canada and elsewhere. Airborne wood dust concentration ranged between 0.001 mg/m³ and 4.87 mg/m³ as total dust and noise exposure ranged between 55 and 117 dB(A). The study indicates the need for a more comprehensive industry-wide study of wood dust, noise, and bioaersols.

Occupational Health and Safety Issues in Ontario Sawmills and Veneer/Plywood Plants: A Pilot Study

Directory of Open Access Journals (Sweden)

Dave K. Verma

2010-01-01

Full Text Available A pilot study was conducted within the Ontario sawmill and veneer/plywood manufacturing industry. Information was collected by postal questionnaire and observational walk-through surveys. Industrial hygiene walk-through surveys were conducted at 22 work sites, and measurements for wood dust, noise, and bioaerosol were taken. The aim of the study was to obtain data on the current status regarding health and safety characteristics and an estimate of wood dust, noise, and bioaerosol exposures. The occupational exposure to wood dust and noise are similar to what has been reported in this industry in Canada and elsewhere. Airborne wood dust concentration ranged between 0.001 mg/m3 and 4.87 mg/m3 as total dust and noise exposure ranged between 55 and 117 dB(A. The study indicates the need for a more comprehensive industry-wide study of wood dust, noise, and bioaersols.

Study on some safety-related aspects of tyre use

NARCIS (Netherlands)

Jansen, S.T.H.; Schmeitz, A.J.C.; Maas, S.; Rodarius, C.; Akkermans, L.

2014-01-01

The tyre is a key component that affects road safety. The European commission has posted a tender aimed to study what measures on a European level can be taken in relation to the use of tyres to improve road safety. The results of this study, supported by a cost benefit analyses and carried out by

Food Safety at Farmers' Markets: A Knowledge Synthesis of Published Research.

Science.gov (United States)

Young, Ian; Thaivalappil, Abhinand; Reimer, Danielle; Greig, Judy

2017-12-01

Farmers' markets are increasingly popular venues in North America for the sale of fresh produce and other foods. However, the nature of their operation can present possible food safety issues, challenges, and risks to consumers. A knowledge synthesis was conducted to identify, characterize, and summarize published research on the microbial food safety issues and implications associated with farmers' markets. A scoping review was conducted using the following steps: comprehensive search strategy, relevance screening of abstracts, and characterization of relevant articles. Two subsets of data were prioritized for more detailed systematic review (data extraction and risk-of-bias assessment) and meta-analysis: (i) studies comparing the microbial safety of foods from farmers' markets versus other sources and (ii) studies evaluating the use of food safety practices at farmers' markets. Overall, 83 relevant studies were identified. The majority of studies were published as journal articles (64%), used a cross-sectional design (81%), and were conducted in the United States (78%). Most studies (39%; n = 32) investigated stakeholder, mostly consumer (n = 22), attitudes toward food safety at farmers' markets. Limited but heterogeneous evidence indicated a higher prevalence of Campylobacter and Salmonella in chicken meat from farmers' markets versus other retail sources, but there was no difference in the microbial contamination of fresh produce. Studies evaluating the use of food safety practices at farmers' markets identified some gaps; for example, the average prevalence of vendor hand washing was 4% (95% confidence interval: 0 to 11%; I 2 = 27%; n = 5 studies). Twelve foodborne outbreaks and case reports were identified, resulting in a total of 411 illnesses, 38 hospitalizations, and two deaths from 1994 to 2016. Only five intervention studies were identified. Key knowledge gaps and areas warranting future research, training, and education are highlighted and discussed.

A study of software safety analysis system for safety-critical software

International Nuclear Information System (INIS)

Chang, H. S.; Shin, H. K.; Chang, Y. W.; Jung, J. C.; Kim, J. H.; Han, H. H.; Son, H. S.

2004-01-01

The core factors and requirements for the safety-critical software traced and the methodology adopted in each stage of software life cycle are presented. In concept phase, Failure Modes and Effects Analysis (FMEA) for the system has been performed. The feasibility evaluation of selected safety parameter was performed and Preliminary Hazards Analysis list was prepared using HAZOP(Hazard and Operability) technique. And the check list for management control has been produced via walk-through technique. Based on the evaluation of the check list, activities to be performed in requirement phase have been determined. In the design phase, hazard analysis has been performed to check the safety capability of the system with regard to safety software algorithm using Fault Tree Analysis (FTA). In the test phase, the test items based on FMEA have been checked for fitness guided by an accident scenario. The pressurizer low pressure trip algorithm has been selected to apply FTA method to software safety analysis as a sample. By applying CASE tool, the requirements traceability of safety critical system has been enhanced during all of software life cycle phases

Personal Safety and Teacher/Student Relationships Viewed through Black/White Framework in a Suburban Middle School, an Exploratory Study

Science.gov (United States)

Mester, Dana C.; Spruill, Sherill A.; Giani, Joseph; Morote, Elsa-Sofia; Inserra, Albert

2015-01-01

This study explored the perceptions of teacher-student relationships and personal student safety differences between Caucasian and African-American middle school students. The research was conducted using a survey in a suburban middle class school on Long Island, New York. Twenty-eight of 176 Caucasian students were chosen through random sampling…

Safety Assessment in Installation of Precast Concrete

Directory of Open Access Journals (Sweden)

Yashrri S.N.

2014-03-01

Full Text Available This study was carried out to identify the safety aspects and the level of safety during the installation process in construction sites. A questionnaire survey and interviews were done to provide data on safety requirements in precast concrete construction. All of the interviews and the research questionnaire survey were conducted among contractors that are registered as class 1 to class 7 with the Construction Industry Development Board (CIDB and class A to class G with Pusat Khidmat Kontraktor (PKK in Penang. Returned questionnaires were analysed with the use of simple percentages and the Likert Scale analysis method to identify safety aspects of precast construction. The results indicate that the safety aspect implemented by companies involved in the precast construction process is at a good level in the safety aspect during bracing, propping, welding and grouting processes and at a very good level of safety in general aspects and safety aspects during lifting processes.

Ways of improving safety for future PWRs in France

International Nuclear Information System (INIS)

Gros, G.; Jalouneix, J.; Manesse, D.; Mattei, J.M.

1994-06-01

Results of thinkings and studies, conducted within the Institute for Nuclear Safety and Protection (IPSN) on various fields of nuclear power plant safety, on the definition of safety objectives and principles for future PWRs. The aim of the studies is to identify ways of improving the design of future plants in France and Germany, with the main following objectives: significant reduction of the global probability of core damage, significant reduction of radioactive releases, mainly for severe accident conditions, and reduction of individual and collective doses received by workers. (R.P.) 3 refs., 1 tab

Migration, violence, and safety among migrant sex workers: A qualitative study in two Guatemalan communities

OpenAIRE

Rocha-Jiménez, Teresita; Brouwer, Kimberly C.; Silverman, Jay G.; Morales-Miranda, Sonia; Goldenberg, Shira M.

2016-01-01

Despite reports of high levels of violence among women migrants in Central America, limited evidence exists regarding the health and safety of migrant sex workers in Central America. This study is based on 16 months of field research (November 2012–February 2015), including ethnographic fieldwork, in-depth interviews, and focus groups conducted with 52 internal and international migrant female sex workers in Tecún Úman and Quetzaltenango, Guatemala, key transit and destination communities for...

A Methodology for Safety Culture Impact Assessment

Energy Technology Data Exchange (ETDEWEB)

Han, Kiyoon; Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of)

2014-05-15

The purpose of this study is to develop methodology for assessing safety culture impact on nuclear power plants. A new methodology for assessing safety culture impact index has been developed and applied for the reference nuclear power plants. The developed SCII model might contribute to comparing the level of safety culture among nuclear power plants as well as to improving the safety of nuclear power plants. Safety culture is defined to be fundamental attitudes and behaviors of the plant staff which demonstrate that nuclear safety is the most important consideration in all activities conducted in nuclear power operation. Through several accidents of nuclear power plant including the Fukusima Daiichi in 2011 and Chernovyl accidents in 1986, the safety of nuclear power plant is emerging into a matter of interest. From the accident review report, it can be easily found out that safety culture is important and one of dominant contributors to accidents. However, the impact methodology for assessing safety culture has not been established analytically yet. It is difficult to develop the methodology for assessing safety culture impact quantitatively.

A Methodology for Safety Culture Impact Assessment

International Nuclear Information System (INIS)

Han, Kiyoon; Jae, Moosung

2014-01-01

The purpose of this study is to develop methodology for assessing safety culture impact on nuclear power plants. A new methodology for assessing safety culture impact index has been developed and applied for the reference nuclear power plants. The developed SCII model might contribute to comparing the level of safety culture among nuclear power plants as well as to improving the safety of nuclear power plants. Safety culture is defined to be fundamental attitudes and behaviors of the plant staff which demonstrate that nuclear safety is the most important consideration in all activities conducted in nuclear power operation. Through several accidents of nuclear power plant including the Fukusima Daiichi in 2011 and Chernovyl accidents in 1986, the safety of nuclear power plant is emerging into a matter of interest. From the accident review report, it can be easily found out that safety culture is important and one of dominant contributors to accidents. However, the impact methodology for assessing safety culture has not been established analytically yet. It is difficult to develop the methodology for assessing safety culture impact quantitatively

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 10, March 2009

International Nuclear Information System (INIS)

2009-03-01

The current issue contains information about the following meetings: Application of the Code of Conduct on the Safety of Research Reactors (the 'Code'). Environmental Modelling for Radiation Safety (EMRAS II); Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The document also gives an overview on International Nuclear Security Advisory Service (INSServ)

Assessment of Contributions to Patient Safety Knowledge by the Agency for Healthcare Research and Quality-Funded Patient Safety Projects

Science.gov (United States)

Sorbero, Melony E S; Ricci, Karen A; Lovejoy, Susan; Haviland, Amelia M; Smith, Linda; Bradley, Lily A; Hiatt, Liisa; Farley, Donna O

2009-01-01

Objective To characterize the activities of projects funded in Agency for Healthcare Research and Quality (AHRQ)' patient safety portfolio and assess their aggregate potential to contribute to knowledge development. Data Sources Information abstracted from proposals for projects funded in AHRQ' patient safety portfolio, information on safety practices from the AHRQ Evidence Report on Patient Safety Practices, and products produced by the projects. Study Design This represented one part of the process evaluation conducted as part of a longitudinal evaluation based on the Context–Input–Process–Product model. Principal Findings The 234 projects funded through AHRQ' patient safety portfolio examined a wide variety of patient safety issues and extended their work beyond the hospital setting to less studied parts of the health care system. Many of the projects implemented and tested practices for which the patient safety evidence report identified a need for additional evidence. The funded projects also generated a substantial body of new patient safety knowledge through a growing number of journal articles and other products. Conclusions The projects funded in AHRQ' patient safety portfolio have the potential to make substantial contributions to the knowledge base on patient safety. The full value of this new knowledge remains to be confirmed through the synthesis of results. PMID:21456108

Supplement to safety analysis report. 306-W building operations safety requirement

International Nuclear Information System (INIS)

Richey, C.R.

1979-08-01

The operations safety requirements (OSRs) presented in this report define the conditions, safe boundaries, and management control needed for safely conducting operations with radioactive materials in the Pacific Northwest Laboratory (PNL) 306-W building. The safety requirements are organized in five sections. Safety limits are safety-related process variables that are observable and measurable. Limiting conditions cover: equipment and technical conditions and characteristics of the facility and operations necessary for continued safe operation. Surveillance requirements prescribe the requirements for checking systems and components that are essential to safety. Equipment design controls require that changes to process equipment and systems be independently checked and approved to assure that the changes will have no adverse effect on safety. Administrative controls describe and discuss the organization and administrative systems and procedures to be used for safe operation of the facility. Details of the implementation of the operations safety requirements are prescribed by internal PNL documents such as criticality safety specifications and radiation work procedures

Innovation and Safety. A prestudy

International Nuclear Information System (INIS)

Rollenhagen, Carl; Hansson, Sven Ove; Hortberg, Johan; Jakobsson, Fredrik; Zhau, Victoria Jing; Mojeri, Sara

2010-04-01

The project summarized in this report was initiated to explore relations between innovation and safety. The first two sections of the report discuss some previously conducted research and give a general background to the subject. It is concluded that safety research and innovation research, by and large, has developed as separate academic disciplines. The concepts of 'innovative safety culture' and 'safe innovation cultures' are suggested as two concepts that can be used to integrate research: innovative safety cultures depart from safety culture research but attempts to introduce an innovative dimension with the aim to create adaptive and innovative safety cultures that efficiently can handle risks arising from existing innovations. Safe innovation cultures have focus on innovation itself, but with the ambition to introduce concepts and methods from safety research in the innovative processes. Three subprojects conducted in the context of the present research are summarized. The first project examines how an existing organization (e.g. SKB - Swedish Nuclear Fuel and Waste Management) attempts to integrate both innovative activities and operative activities in the same organisation. Interviews with key personnel explored different views about how innovative and safety work coexists in the organisation. The second project focuses on how major retrofit projects of a nuclear power plant is managed in parallel to operative activities (e.g. operating the plant on an everyday basis). By means of an innovative technique (e.g. system groups) seminars were held to suggest improvements in the technical change process. The third project conducted a risk analysis of a major organisational change (e.g. control centres for energy distribution). Experiences from the three projects are finally discussed in terms of similarities and differences associated with the cultures for innovation and safety. Suggestions for further research are made

Age and workers' perceptions of workplace safety: a comparative study.

Science.gov (United States)

Gyekye, Seth Ayim; Salminen, Simo

2009-01-01

The study examined the relationship between age and (i) safety perception; (ii) job satisfaction; (iii) compliance with safety management policies; and (iv) accident frequency. Participants were Ghanaian industrial workers (N=320) categorized into 4 age groups: 19-29 years; 30-39 years; 40-50 years; and 51 years and above. Workplace safety perception was assessed with Hayes, Perander, Smecko, and Trask's (1998) 50-item Work Safety Scale (WSS): a scale that effectively captures the dimensions identified by safety experts to influence perceptions of workplace safety. ANOVA was used to test for differences in the mean scores of the 4 groups. Post Hoc analysis revealed differences of statistical significance between the 2 younger cohorts and the 2 older cohorts. The results indicated a positive association between age and safety perception. Older workers had the best perceptions on safety, indicated the highest level of job satisfaction, were the most compliant with safety procedures, and recorded the lowest accident involvement rate. From a practical perspective, understanding age-related perceptions of workplace safety would benefit management's decisions regarding workers' adaptability, general work effectiveness, accident frequency, implementation of safety management policies, and handling of age-related accident characteristics.

Safety and feasibility of transcranial direct current stimulation in pediatric hemiparesis: randomized controlled preliminary study.

Science.gov (United States)

Gillick, Bernadette T; Feyma, Tim; Menk, Jeremiah; Usset, Michelle; Vaith, Amy; Wood, Teddi Jean; Worthington, Rebecca; Krach, Linda E

2015-03-01

Transcranial direct current stimulation (tDCS) is a form of noninvasive brain stimulation that has shown improved adult stroke outcomes. Applying tDCS in children with congenital hemiparesis has not yet been explored. The primary objective of this study was to explore the safety and feasibility of single-session tDCS through an adverse events profile and symptom assessment within a double-blind, randomized placebo-controlled preliminary study in children with congenital hemiparesis. A secondary objective was to assess the stability of hand and cognitive function. A double-blind, randomized placebo-controlled pretest/posttest/follow-up study was conducted. The study was conducted in a university pediatric research laboratory. Thirteen children, ages 7 to 18 years, with congenital hemiparesis participated. Adverse events/safety assessment and hand function were measured. Participants were randomly assigned to either an intervention group or a control group, with safety and functional assessments at pretest, at posttest on the same day, and at a 1-week follow-up session. An intervention of 10 minutes of 0.7 mA tDCS was applied to bilateral primary motor cortices. The tDCS intervention was considered safe if there was no individual decline of 25% or group decline of 2 standard deviations for motor evoked potentials (MEPs) and behavioral data and no report of adverse events. No major adverse events were found, including no seizures. Two participants did not complete the study due to lack of MEP and discomfort. For the 11 participants who completed the study, group differences in MEPs and behavioral data did not exceed 2 standard deviations in those who received the tDCS (n=5) and those in the control group (n=6). The study was completed without the need for stopping per medical monitor and biostatisticial analysis. A limitation of the study was the small sample size, with data available for 11 participants. Based on the results of this study, tDCS appears to be safe

IAEA safety requirements for safety assessment of fuel cycle facilities and activities

International Nuclear Information System (INIS)

Jones, G.

2013-01-01

The IAEA's Statute authorises the Agency to establish standards of safety for protection of health and minimisation of danger to life and property. In that respect, the IAEA has established a Safety Fundamentals publication which contains ten safety principles for ensuring the protection of workers, the public and the environment from the harmful effects of ionising radiation. A number of these principles require safety assessments to be carried out as a means of evaluating compliance with safety requirements for all nuclear facilities and activities and to determine the measures that need to be taken to ensure safety. The safety assessments are required to be carried out and documented by the organisation responsible for operating the facility or conducting the activity, are to be independently verified and are to be submitted to the regulatory body as part of the licensing or authorisation process. In addition to the principles of the Safety Fundamentals, the IAEA establishes requirements that must be met to ensure the protection of people and the environment and which are governed by the principles in the Safety Fundamentals. The IAEA's Safety Requirements publication 'Safety Assessment for Facilities and Activities', establishes the safety requirements that need to be fulfilled in conducting and maintaining safety assessments for the lifetime of facilities and activities, with specific attention to defence in depth and the requirement for a graded approach to the application of these safety requirements across the wide range of fuel cycle facilities and activities. Requirements for independent verification of the safety assessment that needs to be carried out by the operating organisation, including the requirement for the safety assessment to be periodically reviewed and updated are also covered. For many fuel cycle facilities and activities, environmental impact assessments and non-radiological risk assessments will be required. The

Conducting Simulation Studies in Psychometrics

Science.gov (United States)

Feinberg, Richard A.; Rubright, Jonathan D.

2016-01-01

Simulation studies are fundamental to psychometric discourse and play a crucial role in operational and academic research. Yet, resources for psychometricians interested in conducting simulations are scarce. This Instructional Topics in Educational Measurement Series (ITEMS) module is meant to address this deficiency by providing a comprehensive…

Main lessons for FBR safety study from the CABRI experiments

International Nuclear Information System (INIS)

Sato, Ikken

2006-01-01

CABRI project has been carried out FBR safety study with international cooperation of five nations since 1978. The project consists of four periods such as CABRI-1, CABRI-2, CABRI-FAST and CABRI-RAFT. The objects and the main information for hypothetical core decay accident and safety study of fuel are described. The behavior of core decay accident was studied in the first period (CABRI-1), the safety study of fuel was investigated after the second period (CABRI-2). Change of phenomena at the initial process of core decay accident, comparison between analysis and data of fuel diffusion behavior of neutron horoscope by CABRI-2 experiment, representative in-core experiment under slow TOP conditions, the damaged and undamaged pin under slow TOP conditions, the exterior of CABRI and TREAT and the upper part of CABRI and TREAT reactor are shown. CABRI experiments changed to LWR safety study and a part of TREAT is stated. (S.Y.)

Ways of improving safety for future PWRs in France

International Nuclear Information System (INIS)

Gros, G.; Jalouneix, J.; Manesse, D.; Mattei, J.M.

1994-01-01

For the design of a new generation of nuclear power plants which could be ordered in France at the end of the nineties, there is a broad consensus on the choice of the evolutionary way, in view of the significant progress in the field of safety which appears possible with this approach, due to feedback of operating experience from a large number of reactors, results of extended safety research and development projects, general technical progress and findings from detailed probabilistic safety studies performed. This paper presents results of thinkings and studies, conducted within the Institute for Nuclear Safety and Protection (IPSN) in the various fields mentioned, in view of the definition of safety objectives and principles for future PWRs. These results contributed to the preparation of a common safety approach for future plants in France and Germany. (authors). 1 tab., 3 refs

Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

International Nuclear Information System (INIS)

Chung, Dae Wook

2011-01-01

Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

Some recent studies on the main threats from the outside and safety recommendations adapted to the European situation

International Nuclear Information System (INIS)

Doury, A.; Barbreau, A.; Gerard, R.

1975-01-01

With a view to the formulation of safety recommendations accounting for any factors peculiar to the European situation in the matter of nuclear plant sites, the Nuclear Safety Department of the Commissariat a l'Energie Atomique is conducting a special research programme of a mainly meteorological and seismological nature. The most important of the studies now in progress concern the external threats or restrictions to which the plants may be subjected because of the site itself or its environment. The possible outside dangers to be taken most seriously in Europe are probably explosions of gas layers from the industrial environment, and severe earthquakes. The main features of recent or current research on these two kinds of threat are outlined, with an indication of the chief practical results already obtained or anticipated in the matter of safety improvement [fr

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

Management commitment to safety as organizational support: relationships with non-safety outcomes in wood manufacturing employees

Science.gov (United States)

Judd H. Michael; Demetrice D. Evans; Karen J. Jansen; Joel M. Haight

2005-01-01

Employee perceptions of management commitment to safety are known to influence important safety-related outcomes. However, little work has been conducted to explore nonsafety-related outcomes resulting from a commitment to safety. Method: Employee-level outcomes critical to the effective functioning of an organization, including attitudes such as job...

Identifying the Critical Factors Affecting Safety Program Performance for Construction Projects within Pakistan Construction Industry

Directory of Open Access Journals (Sweden)

Zubair Ahmed Memon

2013-04-01

Full Text Available Many studies have shown that the construction industry one of the most hazardous industries with its high rates of fatalities and injuries and high financial losses incurred through work related accident. To reduce or overcome the safety issues on construction sites, different safety programs are introduced by construction firms. A questionnaire survey study was conducted to highlight the influence of the Construction Safety Factors on safety program implementation. The input from the questionnaire survey was analyzed by using AIM (Average Index Method and rank correlation test was conducted between different groups of respondents to measure the association between different groups of respondent. The finding of this study highlighted that management support is the critical factor for implementing the safety program on projects. From statistical test, it is concluded that all respondent groups were strongly in the favor of management support factor as CSF (Critical Success Factor. The findings of this study were validated on selected case studies. Results of the case studies will help to know the effect of the factors on implementing safety programs during the execution stage.

Determinants of Knowledge and Safety Practices of Occupational Hazards of Textile Dye Workers in Sokoto, Nigeria: A Descriptive Analytic Study.

Science.gov (United States)

Okafoagu, Nneka Christina; Oche, Mansur; Awosan, Kehinde Joseph; Abdulmulmuni, Hashim Bala; Gana, Godwin Jiya; Ango, Jessica Timane; Raji, Ismail

2017-06-23

Textile dye workers are subject to occupational hazards on a daily basis due to exposure to precarious conditions in the workplace. This study aimed to assess the knowledge, attitude and safety practices and its determinants among textile dye workers in Sokoto metropolis, Nigeria. This is a descriptive cross-sectional study conducted among 200 textile dye workers and the respondents were selected by multi stage sampling technique. Data was collected using an interviewer administered questionnaire. Data was processed using SPSS IBM version 20 and analyzed using descriptive and inferential statistics. Majority of the respondents (74.0%) had good knowledge of workplace hazards; (81.0%) had positive attitude and only 20% observed all the safety practices. Formal education (P=0.047); working less than 5 days a week (P=0.001) and permanent employment (P=0.013) were found to be determinants of respondents' knowledge and attitude towards workplace hazards. Although the respondents had good knowledge and positive attitude, their lack of observance of safety practices brings to fore the need for direct safety instruction and training and retraining of textile dye workers on workplace hazards and safety practices.

Technical Safety Appraisal of the Rocky Flats Plant

Energy Technology Data Exchange (ETDEWEB)

Brown, Blake P.

1989-01-01

This report provides the results of a Technical Safety Appraisal (TSA) of the Rocky Flats Plant (RFP) conducted November 14 to 18 and November 28 to December 9, 1988. This appraisal covered the effectiveness and improvements in the RFP safety program across the site, evaluating progress to date against standards of accepted practice. The appraisal included coverage of the timeliness and effectiveness of actions taken in response to the recommendations/concerns in three previous Technical Safety Appraisals (TSAs) of RFP Bldg. 707 conducted in July 1986, Bldgs. 771/774 conducted in October/November 1986, and Bldgs. 776/777 conducted in January/February 1988. Results of this appraisal are given in Section IV for each of 14 technical safety areas at RFP. These results include a discussion, conclusions and any new safety concerns for each technical safety area. Appendix A contains a description of the system for categorizing concerns, and the concerns are tabulated in Appendix B. Appendix C reports on the evaluation of the contractor's actions and the current status of each of the 230 recommendations and concerns contained in the three previous TSA reports.

Status of conceptual safety design study of Japanese sodium-cooled fast reactor

International Nuclear Information System (INIS)

Kubo, Shigenobu; Kurisaka, Kenichi; Niwa, Hajime; Shimakawa, Yoshio

2005-01-01

In this paper, the current conceptual safety design and related evaluation of Japanese Sodium-cooled Fast Reactor which is studied in the framework of the Feasibility Study (FS) on commercialized Fast Reactor Cycle Systems in Japan are described. The purpose of the safety design is to establish a feasible safety concept of FBR which aims at a sustainable energy source of the next generations. The safety targets and the safety design principle are set aiming at realizing worldwide acceptability of the safety level. The basic safety design concept, which can meet the safety targets, was formulated taking along with the defense-in-depth philosophy as the basic safety design principle. In order to cope with wide range of energy and resource demands, there are some various designs both of oxide and metal fuel for JSFR. Some analytical results of typical design basis events, design extension conditions and core damage frequency estimation show the feasibility of the safety design concept for them. (author)

Integration of Active and Passive Safety Technologies--A Method to Study and Estimate Field Capability.

Science.gov (United States)

Hu, Jingwen; Flannagan, Carol A; Bao, Shan; McCoy, Robert W; Siasoco, Kevin M; Barbat, Saeed

2015-11-01

The objective of this study is to develop a method that uses a combination of field data analysis, naturalistic driving data analysis, and computational simulations to explore the potential injury reduction capabilities of integrating passive and active safety systems in frontal impact conditions. For the purposes of this study, the active safety system is actually a driver assist (DA) feature that has the potential to reduce delta-V prior to a crash, in frontal or other crash scenarios. A field data analysis was first conducted to estimate the delta-V distribution change based on an assumption of 20% crash avoidance resulting from a pre-crash braking DA feature. Analysis of changes in driver head location during 470 hard braking events in a naturalistic driving study found that drivers' head positions were mostly in the center position before the braking onset, while the percentage of time drivers leaning forward or backward increased significantly after the braking onset. Parametric studies with a total of 4800 MADYMO simulations showed that both delta-V and occupant pre-crash posture had pronounced effects on occupant injury risks and on the optimal restraint designs. By combining the results for the delta-V and head position distribution changes, a weighted average of injury risk reduction of 17% and 48% was predicted by the 50th percentile Anthropomorphic Test Device (ATD) model and human body model, respectively, with the assumption that the restraint system can adapt to the specific delta-V and pre-crash posture. This study demonstrated the potential for further reducing occupant injury risk in frontal crashes by the integration of a passive safety system with a DA feature. Future analyses considering more vehicle models, various crash conditions, and variations of occupant characteristics, such as age, gender, weight, and height, are necessary to further investigate the potential capability of integrating passive and DA or active safety systems.

Seismic and tsunami safety margin assessment

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Nuclear Regulation Authority is going to establish new seismic and tsunami safety guidelines to increase the safety of NPPs. The main purpose of this research is testing structures/components important to safety and tsunami resistant structures/components, and evaluating the capacity of them against earthquake and tsunami. Those capacity data will be utilized for the seismic and tsunami back-fit review based on the new seismic and tsunami safety guidelines. The summary of the program in 2012 is as follows. 1. Component seismic capacity test and quantitative seismic capacity evaluation. PWR emergency diesel generator partial-model seismic capacity tests have been conducted and quantitative seismic capacities have been evaluated. 2. Seismic capacity evaluation of switching-station electric equipment. Existing seismic test data investigation, specification survey and seismic response analyses have been conducted. 3. Tsunami capacity evaluation of anti-inundation measure facilities. Tsunami pressure test have been conducted utilizing a small breakwater model and evaluated basic characteristics of tsunami pressure against seawall structure. (author)

Seismic and tsunami safety margin assessment

International Nuclear Information System (INIS)

2013-01-01

Nuclear Regulation Authority is going to establish new seismic and tsunami safety guidelines to increase the safety of NPPs. The main purpose of this research is testing structures/components important to safety and tsunami resistant structures/components, and evaluating the capacity of them against earthquake and tsunami. Those capacity data will be utilized for the seismic and tsunami back-fit review based on the new seismic and tsunami safety guidelines. The summary of the program in 2012 is as follows. 1. Component seismic capacity test and quantitative seismic capacity evaluation. PWR emergency diesel generator partial-model seismic capacity tests have been conducted and quantitative seismic capacities have been evaluated. 2. Seismic capacity evaluation of switching-station electric equipment. Existing seismic test data investigation, specification survey and seismic response analyses have been conducted. 3. Tsunami capacity evaluation of anti-inundation measure facilities. Tsunami pressure test have been conducted utilizing a small breakwater model and evaluated basic characteristics of tsunami pressure against seawall structure. (author)

Fusion Safety Program annual report, fiscal year 1994

International Nuclear Information System (INIS)

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

1995-03-01

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

Studies on Labour Safety in Construction Sites

Directory of Open Access Journals (Sweden)

S. Kanchana

2015-01-01

Full Text Available Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites.

Studies on Labour Safety in Construction Sites

Science.gov (United States)

Kanchana, S.; Sivaprakash, P.; Joseph, Sebastian

2015-01-01

Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites. PMID:26839916

Chemical Safety Vulnerability Working Group Report

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

This report marks the culmination of a 4-month review conducted to identify chemical safety vulnerabilities existing at DOE facilities. This review is an integral part of DOE's efforts to raise its commitment to chemical safety to the same level as that for nuclear safety.

Promoting personal safety of building service workers: issues and challenges.

Science.gov (United States)

Chen, Shelley I; Skillen, D Lynn

2006-06-01

This exploratory, descriptive study conducted at a large western Canadian university solicited perceptions of personal safety among building service workers who perform night shift work alone. Ten semi-structured interviews were conducted at approximately 10:00 p.m. or 7:00 a.m with a convenience sample of night building service workers in private or semi-private locations on the university campus. Transcribed interview data were subjected to inductive content analysis using descriptive, interpretive, and pattern coding (Miles & Huberman, 1994). Results suggest that building service night shift workers are exposed to personal safety hazards in their physical and psychosocial work environments. In addition, culturally and linguistically appropriate delivery of safety training and education about policies and procedures is required for culturally diverse building service workers. Promotion of personal safety in this heterogeneous worker population requires due diligence, assessment, and advocacy.

A Study of Coal Miners’ Safety Psychological Elements Based on Questionnaire Survey

Directory of Open Access Journals (Sweden)

Li Zeng-bo

2016-01-01

Full Text Available During the production process, the instability of safety psychological elements of coal miners contributes to unsafe behaviors that may result in fatal accident. To search the dominant psychological elements, three types of unsafe psychology, comprising 18 unsafe psychological elements, are obtained by theoretical analysis and site survey. Then, an assessment model is established, and a matched questionnaire is applied to two large modern coal mines in Inner Mongolia Autonomous Region. Based on questionnaire survey results and analytic hierarchy process (AHP, assessment judgment matrixes are constructed, effect weight is calculated, and consistency check is conducted. The analysis results show that safety psychology elements of defective type are the dominant elements that trigger unsafe behaviors of coal miners.

Post-marketing safety surveillance conducted in Korea (2008-2013) following the introduction of the rotavirus vaccine, RIX4414 (Rotarix™).

Science.gov (United States)

Shin, Son Moon; Kim, Chun Soo; Karkada, Naveen; Liu, Aixue; Jayadeva, Girish; Han, Htay Htay

2016-10-02

According to regulations from the Ministry of Food and Drug Safety in Korea, additional safety information on the use of Rotarix™ vaccine (RIX4414; GSK, Belgium) in ≥3000 evaluable Korean infants was required following vaccine registration. In order to comply with these regulations, we conducted a 6-year open, non-comparative, multicenter post-marketing surveillance (NCT00750893). During this time, the original lyophilized vaccine formulation of RIX4414 was replaced by a liquid formulation. Healthy infants aged ≥6 weeks were enrolled and given 2 doses of the RIX4414 vaccine, separated by an interval of ≥4 weeks. The overall incidence of adverse events (AEs) (expected and unexpected) was then assessed for up to 30 days along with the incidence of serious adverse events (SAEs). Adverse drug reactions (ADRs: any AE whose causality to the drug could not be ruled out) were identified. A total of 3040 children (mean age: 9.55 weeks) were analyzed. One or more expected AE was experienced by 30.5% infants and 8.6% had an ADR. The most commonly seen expected AE was irritability (14.0%). One or more unexpected AE was seen in 32.5% infants and 3.1% experienced an ADR. The most commonly seen unexpected AE was upper respiratory tract infection (8.7%). Of 34 SAEs recorded in 24 subjects, none were related to vaccination. We conclude that this 6-year surveillance showed both formulations of RIX4414 to have acceptable safety profiles when administered to Korean infants according to local prescribing recommendations and current clinical practice.

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.

Fusion Safety Program annual report, Fiscal Year 1993

International Nuclear Information System (INIS)

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

1993-12-01

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

Study of thermal conductivity of multilayer insulation

International Nuclear Information System (INIS)

Dutta, D.; Sundaram, S.; Nath, G.K.; Sethuram, N.P.; Chandrasekharan, T.; Varadarajan, T.G.

1994-01-01

This paper presents experimental determination of the apparent thermal conductivity of multilayer insulation for a cryogenic system. The variation of thermal conductivity with residual gas pressure is studied and the optimum vacuum for good insulating performance is determined. Evaporation loss technique for heat-inleak determination is employed. (author)

Evaluation of Patient Safety Culture and Organizational Culture as a Step in Patient Safety Improvement in a Hospital in Jakarta, Indonesia

Directory of Open Access Journals (Sweden)

Afrisya Iriviranty

2016-07-01

Full Text Available Introduction: Establishment of patient safety culture is the first step in the improvement of patient safety. As such, assessment of patient safety culture in hospitals is of paramount importance. Patient safety culture is an inherent component of organizational culture, so that the study of organizational culture is required in developing patient safety. This study aimed to evaluate patient safety culture among the clinical staff of a hospital in Jakarta, Indonesia and identify organizational culture profile. Materials and Methods: This cross-sectional, descriptive, qualitative study was conducted in a hospital in Jakarta, Indonesia in 2014. Sample population consisted of nurses, midwives, physicians, pediatricians, obstetrics and gynecology specialists, laboratory personnel, and pharmacy staff (n=152. Data were collected using the Hospital Survey on Patient Safety Culture developed by the Agency for Healthcare Research and Quality (AHRQ and Organizational Culture Assessment Instrument (OCAI. Results: Teamwork within units” was the strongest dimension of patient safety culture (91.7%, while “staffing” and “non-punitive response to error” were the weakest dimensions (22.7%. Moreover, clan culture was the most dominant type of organizational culture in the studied hospital. This culture serves as a guide for the changes in the healthcare organization, especially in the development of patient safety culture. Conclusion: According to the results of this study, healthcare providers were positively inclined toward the patient safety culture within the organization. As such, the action plan was designed through consensus decision-making and deemed effective in articulating patient safety in the vision and mission of the organization.

Fusion blanket inherent safety assessment

International Nuclear Information System (INIS)

Sze, D.K.; Jung, J.; Cheng, E.T.

1986-01-01

Fusion has significant potential safety advantages. There is a strong incentive for designing fusion plants to ensure that inherent safety will be achieved. Accordingly, both the Tokamak Power Systems Studies and MINIMARS have identified inherent safety as a design goal. A necessary condition is for the blanket to maintain its configuration and integrity under all credible accident conditions. A main problem is caused by afterheat removal in an accident condition. In this regard, it is highly desirable to achieve the required level of protection of the plant capital investment and limitation of radioactivity release by systems that rely only on inherent properties of matter (e.g., thermal conductivity, specific heat, etc.) and without the use of active safety equipment. This paper assesses the conditions under which inherent safety is feasible. Three types of accident conditions are evaluated for two blankets. The blankets evaluated are a self cooled vanadium/lithium blanket and a self-cooled vanadium/Flibe blanket. The accident conditions evaluated are: (1) loss-of-flow accident; (2) loss-of-coolant accident (LOCA); and (3) partial loss-of-coolant accident

Pickering seismic safety margin

International Nuclear Information System (INIS)

Ghobarah, A.; Heidebrecht, A.C.; Tso, W.K.

1992-06-01

A study was conducted to recommend a methodology for the seismic safety margin review of existing Canadian CANDU nuclear generating stations such as Pickering A. The purpose of the seismic safety margin review is to determine whether the nuclear plant has sufficient seismic safety margin over its design basis to assure plant safety. In this review process, it is possible to identify the weak links which might limit the seismic performance of critical structures, systems and components. The proposed methodology is a modification the EPRI (Electric Power Research Institute) approach. The methodology includes: the characterization of the site margin earthquake, the definition of the performance criteria for the elements of a success path, and the determination of the seismic withstand capacity. It is proposed that the margin earthquake be established on the basis of using historical records and the regional seismo-tectonic and site specific evaluations. The ability of the components and systems to withstand the margin earthquake is determined by database comparisons, inspection, analysis or testing. An implementation plan for the application of the methodology to the Pickering A NGS is prepared

Review of light--water reactor safety studies. Volume 3 of health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

International Nuclear Information System (INIS)

Nero, A.V.; Farnaam, M.R.K.

1977-01-01

This report summarizes and compares important studies of light-water nuclear reactor safety, emphasizing the Nuclear Regulatory Commission's Reactor Safety Study, work on risk assessment funded by the Electric Power Research Institute, and the Report of the American Physical Society study group on light-water reactor safety. These reports treat risk assessment for nuclear power plants and provide an introduction to the basic issues in reactor safety and the needs of the reactor safety research program. Earlier studies are treated more briefly. The report includes comments on the Reactor Safety Study. The manner in which these studies may be used and alterations which would increase their utility are discussed

Evaluation and review of the safety management system implementation in the Royal Thai Air Force

Science.gov (United States)

Chaiwan, Sakkarin

This study was designed to determine situation and effectiveness of the safety management system currently implemented in the Royal Thai Air Force. Reviewing the ICAO's SMS and the RTAF's SMS was conducted to identify similarities and differences between the two safety management systems. Later, the researcher acquired safety statistics from the RTAF Safety Center to investigate effectiveness of its safety system. The researcher also collected data to identify other factors affecting effectiveness of the safety system during conducting in-depth interviews. Findings and Conclusions: The study shows that the Royal Thai Air Force has never applied the International Civil Aviation Organization's Safety management System to its safety system. However, the RTAF's SMS and the ICAO's SMS have been developed based on the same concepts. These concepts are from Richard H. Woods's book, Aviation safety programs: A management handbook. However, the effectiveness of the Royal Thai Air Force's safety system is in good stance. An accident rate has been decreasing regularly but there are no known factors to describe the increasing rate, according to the participants' opinion. The participants have informed that there are many issues to be resolved to improve the RTAF's safety system. Those issues are cooperation among safety center's staffs, attitude toward safety of the RTAF senior commanders, and safety standards.

Safety evaluation for the prototype Fast Breeder Reactor MONJU as a Japanese TSO

International Nuclear Information System (INIS)

Endo, Hiroshi

2010-01-01

In the safety field of fast breeder reactors (FBRs), JNES is conducting an evaluation work of the safety regulation by Nuclear and Industry Safety Agency (NISA) for the re-start of a prototype FBR MONJU. MONJU has been stopped over 14 years since 1995 due to a sodium leakage accident at a secondary heat transport system, and is now reached to the criticality on 8th of May, 2010. JNES is supporting the safety regulation work conducted by NISA based on the following activities: i) Support of the technical evaluation of the application for the establishment license prepared by Japan Atomic Energy Agency (JAEA), ii) Support of the description of the safety review report by NISA based on independent safety analyses for the major accident events such as unprotected loss-of-flow (ULOF) by employing the latest findings on the study of core disruptive accidents (CDAs) independently conducted by JNES, iii) Support of the risk-informed-regulation (RIR) such as an accident management (AM) review, iv), and Consideration on the safety regulation policy from the points of severe accidents and source-term behaviors including the cesium (Cs). The objective of this paper is to introduce the major activities of JNES in the safety domain of MONJU regulations. (author)

International standardization of safety requirements for fast reactors

International Nuclear Information System (INIS)

2011-06-01

Japan Atomic Energy Agency (JAEA) is conducting the FaCT (Fast Reactor Cycle Technology Development) project in cooperation with Japan Atomic Power Company (JAPC) and Mitsubishi FBR systems inc. (MFBR), where an advanced loop-type fast reactor named JSFR (Japan Sodium-cooled Fast Reactor) is being developed. It is important to develop software technologies (a safety guideline, safety design criteria, safety design standards etc.) of FBRs as well as hardware ones (a reactor plant itself) in order to address prospective worldwide utilization of FBR technology. Therefore, it is expected to establish a rational safety guideline applicable to the JSFR and harmonized with national nuclear-safety regulations as well, including Japan, the United States and the European Union. This report presents domestic and international status of safety guideline development for sodium-cooled fast reactors (SFRs), results of comparative study for safety requirements provided in existing documents and a proposal for safety requirements of future SFRs with a roadmap for their refinement and worldwide utilization. (author)

Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

International Nuclear Information System (INIS)

2009-01-01

In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

Study of thermal conductivity of multilayer insulation

Energy Technology Data Exchange (ETDEWEB)

Dutta, D; Sundaram, S; Nath, G K; Sethuram, N P; Chandrasekharan, T; Varadarajan, T G [Heavy Water Division, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

This paper presents experimental determination of the apparent thermal conductivity of multilayer insulation for a cryogenic system. The variation of thermal conductivity with residual gas pressure is studied and the optimum vacuum for good insulating performance is determined. Evaporation loss technique for heat-inleak determination is employed. (author). 3 refs., 3 figs.

Study Of Safety Management By Using Gis In Coimbatore

Directory of Open Access Journals (Sweden)

S. Kanchana

2015-08-01

Full Text Available The safety management is very important in the process of construction .The traditional methods of construction safety control cannot meet the construction of big project. To ensure the safety of construction and reduce accidents in the process of construction the current situation and problems we face in construction safety management should be studied first. And then the project risk warning mechanism based on the GIS is constructed according to the problems we faced to achieve visual monitoring and warning of construction safety risk management and to provide decision support for construction. This project aims to develop a web-based spatial decision support system model for proactive health and safety management in linear construction projects. 5 Currently health and safety management is usually performed reactively instead of proactive management since hazard identification and risk assessment is mostly performed on paper based documents that are not effectively used at site. An information system relates to a chain of operations lead to planning the observation and collection of data to storage and analysis of data to the use of derived information in decision-making processes. To create a web-based free and open sourced GIS that can work with different data formats by exchanging and presenting data as a real-time map on web.

A literature review of safety culture.

Energy Technology Data Exchange (ETDEWEB)

Cole, Kerstan Suzanne; Stevens-Adams, Susan Marie; Wenner, Caren A.

2013-03-01

Workplace safety has been historically neglected by organizations in order to enhance profitability. Over the past 30 years, safety concerns and attention to safety have increased due to a series of disastrous events occurring across many different industries (e.g., Chernobyl, Upper Big-Branch Mine, Davis-Besse etc.). Many organizations have focused on promoting a healthy safety culture as a way to understand past incidents, and to prevent future disasters. There is an extensive academic literature devoted to safety culture, and the Department of Energy has also published a significant number of documents related to safety culture. The purpose of the current endeavor was to conduct a review of the safety culture literature in order to understand definitions, methodologies, models, and successful interventions for improving safety culture. After reviewing the literature, we observed four emerging themes. First, it was apparent that although safety culture is a valuable construct, it has some inherent weaknesses. For example, there is no common definition of safety culture and no standard way for assessing the construct. Second, it is apparent that researchers know how to measure particular components of safety culture, with specific focus on individual and organizational factors. Such existing methodologies can be leveraged for future assessments. Third, based on the published literature, the relationship between safety culture and performance is tenuous at best. There are few empirical studies that examine the relationship between safety culture and safety performance metrics. Further, most of these studies do not include a description of the implementation of interventions to improve safety culture, or do not measure the effect of these interventions on safety culture or performance. Fourth, safety culture is best viewed as a dynamic, multi-faceted overall system composed of individual, engineered and organizational models. By addressing all three components of

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

International Nuclear Information System (INIS)

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

1998-12-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-12-01

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

Operational and environmental safety

International Nuclear Information System (INIS)

Anon.

1978-01-01

The responsibility of the DOE Office of Operational and Environmental Safety is to assure that DOE-controlled activities are conducted in a manner that will minimize risks to the public and employees and will provide protection for property and the environment. The program supports the various energy technologies by identifying and resolving safety problems; developing and issuing safety policies, standards, and criteria; assuring compliance with DOE, Federal, and state safety regulations; and establishing procedures for reporting and investigating accidents in DOE operations. Guidelines for the radiation protection of personnel; radiation monitoring at nuclear facilities; an assessment of criticality accidents by fault tree analysis; and the preparation of environmental, safety, and health standards applicable to geothermal energy development are discussed

Multilevel Safety Climate and Safety Performance in the Construction Industry: Development and Validation of a Top-Down Mechanism

Directory of Open Access Journals (Sweden)

Ran Gao

2016-11-01

Full Text Available The character of construction projects exposes front-line workers to dangers and accidents. Safety climate has been confirmed to be a predictor of safety performance in the construction industry. This study aims to explore the underlying mechanisms of the relationship between multilevel safety climate and safety performance. An integrated model was developed to study how particular safety climate factors of one level affect those of other levels, and then affect safety performance from the top down. A questionnaire survey was administered on six construction sites in Vietnam. A total of 1030 valid questionnaires were collected from this survey. Approximately half of the data were used to conduct exploratory factor analysis (EFA and the remaining data were submitted to structural equation modeling (SEM. Top management commitment (TMC and supervisors’ expectation (SE were identified as factors to represent organizational safety climate (OSC and supervisor safety climate (SSC, respectively, and coworkers’ caring and communication (CCC and coworkers’ role models (CRM were identified as factors to denote coworker safety climate (CSC. SEM results show that OSC factor is positively related to SSC factor and CSC factors significantly. SSC factor could partially mediate the relationship between OSC factor and CSC factors, as well as the relationship between OSC factor and safety performance. CSC factors partially mediate the relationship between OSC factor and safety performance, and the relationship between SSC factor and safety performance. The findings imply that a positive safety culture should be established both at the organizational level and the group level. Efforts from all top management, supervisors, and coworkers should be provided to improve safety performance in the construction industry.

Multilevel Safety Climate and Safety Performance in the Construction Industry: Development and Validation of a Top-Down Mechanism.

Science.gov (United States)

Gao, Ran; Chan, Albert P C; Utama, Wahyudi P; Zahoor, Hafiz

2016-11-08

The character of construction projects exposes front-line workers to dangers and accidents. Safety climate has been confirmed to be a predictor of safety performance in the construction industry. This study aims to explore the underlying mechanisms of the relationship between multilevel safety climate and safety performance. An integrated model was developed to study how particular safety climate factors of one level affect those of other levels, and then affect safety performance from the top down. A questionnaire survey was administered on six construction sites in Vietnam. A total of 1030 valid questionnaires were collected from this survey. Approximately half of the data were used to conduct exploratory factor analysis (EFA) and the remaining data were submitted to structural equation modeling (SEM). Top management commitment (TMC) and supervisors' expectation (SE) were identified as factors to represent organizational safety climate (OSC) and supervisor safety climate (SSC), respectively, and coworkers' caring and communication (CCC) and coworkers' role models (CRM) were identified as factors to denote coworker safety climate (CSC). SEM results show that OSC factor is positively related to SSC factor and CSC factors significantly. SSC factor could partially mediate the relationship between OSC factor and CSC factors, as well as the relationship between OSC factor and safety performance. CSC factors partially mediate the relationship between OSC factor and safety performance, and the relationship between SSC factor and safety performance. The findings imply that a positive safety culture should be established both at the organizational level and the group level. Efforts from all top management, supervisors, and coworkers should be provided to improve safety performance in the construction industry.

A comparative study of radiation safety practices at selected hospitals in the UK and USA

International Nuclear Information System (INIS)

White, D.R.; Showalter, C.K.; Hamilton, D.R.

1984-01-01

The radiation safety practices in a group of 25 UK and USA hospitals have recently been assessed. This took the form of detailed inspections of some 62 medical radiation departments, including Diagnostic X-ray, Radiotherapy, Nuclear Medicine and Pathology/Research (Radionuclide) Departments. Empirical expressions called ''Radiation Safety Indices'' were devised to evaluate the incidence of personal doses and radiological incidents occurring from 1977-82 and to characterise the safety facilities, procedures, supervision and educational techniques in each department. An outline is given of national legislative material and voluntary codes of conduct, together with the results of the departmental inspections. The computed indices are presented graphically and an analysis given of apparent national trends. (author)

Nuclear ships and their safety

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-04-15

Several aspects of nuclear ship propulsion, with special reference to nuclear safety, were discussed at an international symposium at Taormina, Italy, from 14-18 November 1960. Discussions on specific topics are conducted, grouped under the following headings: Economics and National Activities in Nuclear Ship Propulsion; International Problems and General Aspects of Safety for Nuclear Ships; Nuclear Ship Projects from the Angle of Safety; Ship Reactor Problems; Sea Motion and Hull Problems; Maintenance and Refuelling Problems; and Safety Aspects of Nuclear Ship Operation.

Food Safety Practices in the Egg Products Industry.

Science.gov (United States)

Viator, Catherine L; Cates, Sheryl C; Karns, Shawn A; Muth, Mary K; Noyes, Gary

2016-07-01

We conducted a national census survey of egg product plants (n = 57) to obtain information on the technological and food safety practices of the egg products industry and to assess changes in these practices from 2004 to 2014. The questionnaire asked about operational and sanitation practices, microbiological testing practices, food safety training for employees, other food safety issues, and plant characteristics. The findings suggest that improvements were made in the industry's use of food safety technologies and practices between 2004 and 2014. The percentage of plants using advanced pasteurization technology and an integrated, computerized processing system increased by almost 30 percentage points. Over 90% of plants voluntarily use a written hazard analysis and critical control point (HACCP) plan to address food safety for at least one production step. Further, 90% of plants have management employees who are trained in a written HACCP plan. Most plants (93%) conduct voluntary microbiological testing. The percentage of plants conducting this testing on egg products before pasteurization has increased by almost 30 percentage points since 2004. The survey findings identify strengths and weaknesses in egg product plants' food safety practices and can be used to guide regulatory policymaking and to conduct required regulatory impact analysis of potential regulations.

Measuring safety climate in elderly homes.

Science.gov (United States)

Yeung, Koon-Chuen; Chan, Charles C

2012-02-01

Provision of a valid and reliable safety climate dimension brings enormous benefits to the elderly home sector. The aim of the present study was to make use of the safety climate instrument developed by OSHC to measure the safety perceptions of employees in elderly homes such that the factor structure of the safety climate dimensions of elderly homes could be explored. In 2010, surveys by mustering on site method were administered in 27 elderly homes that had participated in the "Hong Kong Safe and Healthy Residential Care Home Accreditation Scheme" organized by the Occupational Safety and Health Council. Six hundred and fifty-one surveys were returned with a response rate of 54.3%. To examine the factor structure of safety climate dimensions in our study, an exploratory factor analysis (EFA) using principal components analysis method was conducted to identify the underlying factors. The results of the modified seven-factor's safety climate structure extracted from 35 items better reflected the safety climate dimensions of elderly homes. The Cronbach alpha range for this study (0.655 to 0.851) indicated good internal consistency among the seven-factor structure. Responses from managerial level, supervisory and professional level, and front-line staff were analyzed to come up with the suggestion on effective ways of improving the safety culture of elderly homes. The overall results showed that managers generally gave positive responses in the factors evaluated, such as "management commitment and concern to safety," "perception of work risks and some contributory influences," "safety communication and awareness," and "safe working attitude and participation." Supervisors / professionals, and frontline level staff on the other hand, have less positive responses. The result of the lowest score in the factors - "perception of safety rules and procedures" underlined the importance of the relevance and practicability of safety rules and procedures. The modified OSHC

Occuptional Health and Safety and Employer Motivation

DEFF Research Database (Denmark)

Jensen, Per Langå

2004-01-01

It is often argued and supported by a number of case studies that investment in human factors and occupational health and safety can pay. But any employer has a number of possible in-vestments, and many of these may have a larger marginal utility than health and safety. In addition it is often...... difficult to calculate the exact pay off for human factors and health and safety – how to calculate higher motivation for instance. The economic benefit as a possible driving force for improvement of occupational health and safety is likely to exist but it must be considered a relatively weak force. Another...... important driving force for improvements in health and safety. No employer likes to be ‘branded’ as immoral, manifested in fines by the labour inspectors or media attention to an unsafe conduct. Strategies to im-prove health and safety therefore need to focus on the legitimacy as the probably strongest...

Occupational Health and Safety and Employer Motivation

DEFF Research Database (Denmark)

Hasle, Peter; Jensen, Per Langå

2004-01-01

It is often argued and supported by a number of case studies that investment in human factors and occupational health and safety can pay. But any employer has a number of possible in-vestments, and many of these may have a larger marginal utility than health and safety. In addition it is often...... difficult to calculate the exact pay off for human factors and health and safety – how to calculate higher motivation for instance. The economic benefit as a possible driving force for improvement of occupational health and safety is likely to exist but it must be considered a relatively weak force. Another...... important driving force for improvements in health and safety. No employer likes to be ‘branded’ as immoral, manifested in fines by the labour inspectors or media attention to an unsafe conduct. Strategies to im-prove health and safety therefore need to focus on the legitimacy as the probably strongest...

Product Safety Culture: A New Variant of Safety Culture?

International Nuclear Information System (INIS)

Suhanyiova, L.; Flin, R.; Irwin, A.

2016-01-01

Product safety culture is a new research area which concerns user safety rather than worker or process safety. The concept appears to have emerged after the investigation into the Nimrod aircraft accident (Haddon-Cave, 2009) which echoed aspects of NASA’s Challenger and Columbia crashes. In these cases, through a blend of human and organizational failures, the culture deteriorated to the extent of damaging product integrity, resulting in user fatalities. Haddon-Cave noted that it was due to a failure in leadership and organizational safety culture that accidents such as the Nimrod happened, where the aircraft exploded due to several serious technical failures, preceded by deficiencies in the safety case. Now some organizations are starting to measure product safety culture. This is important in day-to-day life as well, where a product failure as a result of poor organizational safety culture, can cause user harm or death, as in the case of Takata airbags scandal in 2015. Eight people have lost their lives and many were injured. According to investigation reports this was due to the company’s safety malpractices of fixing faulty airbags and proceeding to install them in vehicles, as well as secretly conducting tests to assess the integrity of their product and then deleting the data and denying safety issues as a result of the company’s cost-cutting policies. As such, organizational culture, specifically the applications of safety culture, can have far-reaching consequences beyond the workplace of an organization.

A new assessment method for demonstrating the sufficiency of the safety assessment and the safety margins of the geological disposal system

International Nuclear Information System (INIS)

Ohi, Takao; Kawasaki, Daisuke; Chiba, Tamotsu; Takase, Toshio; Hane, Koji

2013-01-01

A new method for demonstrating the sufficiency of the safety assessment and safety margins of the geological disposal system has been developed. The method is based on an existing comprehensive sensitivity analysis method and can systematically identify the successful conditions, under which the dose rate does not exceed specified safety criteria, using analytical solutions for nuclide migration and the results of a statistical analysis. The successful conditions were identified using three major variables. Furthermore, the successful conditions at the level of factors or parameters were obtained using relational equations between the variables and the factors or parameters making up these variables. In this study, the method was applied to the safety assessment of the geological disposal of transuranic waste in Japan. Based on the system response characteristics obtained from analytical solutions and on the successful conditions, the classification of the analytical conditions, the sufficiency of the safety assessment and the safety margins of the disposal system were then demonstrated. A new assessment procedure incorporating this method into the existing safety assessment approach is proposed in this study. Using this procedure, it is possible to conduct a series of safety assessment activities in a logical manner. (author)

Safety of Bifidobacterium animalis subsp. lactis (B. lactis) strain BB-12-supplemented yogurt in healthy adults on antibiotics: a phase I safety study.

Science.gov (United States)

Merenstein, Daniel J; Tan, Tina P; Molokin, Aleksey; Smith, Keisha Herbin; Roberts, Robert F; Shara, Nawar M; Mete, Mihriye; Sanders, Mary Ellen; Solano-Aguilar, Gloria

2015-01-01

Probiotics are live microorganisms that, when administered in sufficient doses, provide health benefits on the host. The United States Food and Drug Administration (FDA) requires phase I safety studies for probiotics when the intended use of the product is as a drug. The purpose of the study was to determine the safety of Bifidobacterium animalis subsp lactis (B. lactis) strain BB-12 (BB-12)-supplemented yogurt when consumed by a generally healthy group of adults who were prescribed a 10-day course of antibiotics for a respiratory infection. Secondary aims were to assess the ability of BB-12 to affect the expression of whole blood immune markers associated with cell activation and inflammatory response. A phase I, double-blinded, randomized controlled study was conducted in compliance with FDA guidelines for an Investigational New Drug (IND). Forty participants were randomly assigned to consume 4 ounces of either BB-12 -supplemented yogurt or non-supplemented control yogurt daily for 10 d. The primary outcome was to assess safety and tolerability, assessed by the number of reported adverse events. A total of 165 non-serious adverse events were reported, with no differences between the control and BB-12 groups. When compared to the control group, B lactis fecal levels were modestly higher in the BB-12-supplemented group. In a small subset of patients, changes in whole blood expression of genes associated with regulation and activation of immune cells were detected in the BB-12-supplemented group. BB-12-supplemented yogurt is safe and well tolerated when consumed by healthy adults concurrently taking antibiotics. This study will form the basis for future randomized clinical trials investigating the potential immunomodulatory effects of BB-12-supplemented yogurt in a variety of disease states.

Impact of workflow on the use of the Surgical Safety Checklist: a qualitative study.

Science.gov (United States)

Gillespie, Brigid M; Marshall, Andrea P; Gardiner, Therese; Lavin, Joanne; Withers, Teresa K

2016-11-01

Regardless of the benefits associated of the Surgical Safety Checklist, adherence across its three phases remains inconsistent. The aim of this study was to systematically identify issues around workflow that impact on surgical teams' ability to use the Surgical Safety Checklist in a large tertiary facility in Queensland, Australia. Observational audit of 10 surgical teams and 33 semi-structured interviews with 70 participants from nursing, medicine and the community were conducted. Data were collected during 2014-2015. Inductive and deductive approaches were used to analyse field observations and interview transcripts. The domain, impact of workflow on checklist utilization, was identified. Within this domain, seven categories illustrated the causal conditions which determined the ways in which workflow influenced checklist use. These categories included: 'busy doing the task'; 'clashing task priorities'; 'being pressured, running out of time'; 'adapting processes to work patterns'; 'doubling up on work'; 'a domino effect, leading to delays' and 'reality of the workflow'. One of the greatest systemic challenges to checklist use in surgery is workflow. Process changes in the way that surgical safety checklists are used need to incorporate the temporal demands of the workflow. Any changes made must ensure the process is reliable, is easily embedded into existing work routines and is not disruptive. © 2016 Royal Australasian College of Surgeons.

Involvement of patients with cancer in patient safety: a qualitative study of current practices, potentials and barriers.

Science.gov (United States)

Martin, Helle Max; Navne, Laura Emdal; Lipczak, Henriette

2013-10-01

Patient involvement in patient safety is widely advocated but knowledge regarding implementation of the concept in clinical practice is sparse. To investigate existing practices for patient involvement in patient safety, and opportunities and barriers for further involvement. A qualitative study of patient safety involvement practices in patient trajectories for prostate, uterine and colorectal cancer in Denmark. Observations from four hospital wards and interviews with 25 patients with cancer, 11 hospital doctors, 10 nurses, four general practitioners and two private practicing gynaecologists were conducted using ethnographic methodology. Patient safety was not a topic of attention for patients or dominant in communication between patients and healthcare professionals. The understanding of patient safety in clinical practice is almost exclusively linked to disease management. Involvement of patients is not systematic, but healthcare professionals and patients express willingness to engage. Invitation and encouragement of patients to become involved could be further systematised and developed. Barriers include limited knowledge of patient safety, of specific patient safety involvement techniques and concern regarding potential negative impact on doctor-patient relationship. Involvement of patients in patient safety must take into account that despite stated openness to the idea of involvement, patients and health professionals may not in practice show immediate concern. Lack of systematic involvement can also be attributed to limited knowledge about how to implement involvement beyond the focus of self-monitoring and compliance and a concern about the consequences of patient involvement for treatment outcomes. To realise the potential of patients' and health professionals' shared openness towards involvement, there is a need for more active facilitation and concrete guidance on how involvement can be practiced by both parties.

Validation study of safety assessment model for radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Munakata, Masahiro; Takeda, Seiji; Kimura, Hideo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-12-01

The JAERI-AECL collaboration research program has been conducted to validate a groundwater flow and radionuclide transport models for safety assessment. JAERI have developed a geostatistical model for radionuclide transport through a heterogeneous geological media and verify using experimental results of field tracer tests. The simulated tracer plumes explain favorably the experimental tracer plumes. A regional groundwater flow and transport model using site-scale parameter obtained from tracer tests have been verified by comparing simulation results with observation ones of natural environmental tracer. (author)

A mixed methods study of food safety knowledge, practices and beliefs in Hispanic families with young children.

Science.gov (United States)

Stenger, Kristen M; Ritter-Gooder, Paula K; Perry, Christina; Albrecht, Julie A

2014-12-01

Children are at a higher risk for foodborne illness. The objective of this study was to explore food safety knowledge, beliefs and practices among Hispanic families with young children (≤10 years of age) living within a Midwestern state. A convergent mixed methods design collected qualitative and quantitative data in parallel. Food safety knowledge surveys were administered (n = 90) prior to exploration of beliefs and practices among six focus groups (n = 52) conducted by bilingual interpreters in community sites in five cities/towns. Descriptive statistics determined knowledge scores and thematic coding unveiled beliefs and practices. Data sets were merged to assess concordance. Participants were female (96%), 35.7 (±7.6) years of age, from Mexico (69%), with the majority having a low education level. Food safety knowledge was low (56% ± 11). Focus group themes were: Ethnic dishes popular, Relating food to illness, Fresh food in home country, Food safety practices, and Face to face learning. Mixed method analysis revealed high self confidence in preparing food safely with low safe food handling knowledge and the presence of some cultural beliefs. On-site Spanish classes and materials were preferred venues for food safety education. Bilingual food safety messaging targeting common ethnic foods and cultural beliefs and practices is indicated to lower the risk of foodborne illness in Hispanic families with young children. Copyright © 2014 The Authors. Published by Elsevier Ltd.. All rights reserved.

Drivers' opinions of enforcement and incentive strategies to promote safety belt use.

NARCIS (Netherlands)

Hagenzieker, M.P.

2017-01-01

During a nationwide campaign to promote safety belt use among military personnel, a field study was conducted at 12 different military bases in the Netherlands. Amount of enforcement, type of publicity, and incentive strategies were varied among military bases. Observations of safety belt use among

Safety of pressurized water reactors: problems and corresponding studies

International Nuclear Information System (INIS)

Cogne, F.

1976-01-01

The author recalls the safety problems subject to researches in the CEA, either because of their importance or because studies made abroad were not sufficiently developed or were classified or in order to acquire an independent judgement when safety is concerned. Those problems and studies are submitted referring to the 3 existing shields between man and dangerous materials: fuel element can, thermal shield, (pressure vessel and pipes), biological shield of which the behaviour is studied in connection with outside aggressions such as earthquakes, plane crashes, chemical explosions.. [fr

Fusion Safety Program. Annual report, FY 1982

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1983-07-01

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

Abstract of results of safety study. Nuclear fuel cycle field in fiscal 2003

International Nuclear Information System (INIS)

2004-11-01

This report descried the results of studies of nuclear fuel cycle field (nuclear fuel facilities, seismic design, all subjects of environmental radiation and waste disposal, and subjects on nuclear fuel cycle in probabilistic safety assessment) in fiscal 2003 on the basis of the principle project of safety study (from fiscal 2001 to 2005). It consists of four chapters; the first chapter is outline of the principle of project, the second is objects and subjects of safety study in the nuclear fuel cycle field, the third list of questionnaire of results of safety study and the forth investigation of results of safety study in fiscal 2003. There are 49 lists, which include 22 reports on the nuclear fuel facility, one on the seismic design, 4 on the probabilistic safety assessment, 7 on the environmental radiation and 15 on the waste disposal. (S.Y.)

A relational leadership perspective on unit-level safety climate.

Science.gov (United States)

Thompson, Debra N; Hoffman, Leslie A; Sereika, Susan M; Lorenz, Holly L; Wolf, Gail A; Burns, Helen K; Minnier, Tamra E; Ramanujam, Rangaraj

2011-11-01

This study compared nursing staff perceptions of safety climate in clinical units characterized by high and low ratings of leader-member exchange (LMX) and explored characteristics that might account for differences. Frontline nursing leaders' actions are critical to ensure patient safety. Specific leadership behaviors to achieve this goal are underexamined. The LMX perspective has shown promise in nonhealthcare settings as a means to explain safety climate perceptions. Cross-sectional survey of staff (n = 711) and unit directors from 34 inpatient units in an academic medical center was conducted. Significant differences were found between high and low LMX scoring units on supervisor safety expectations, organizational learning-continuous improvement, total communication, feedback and communication about errors, and nonpunitive response to errors. The LMX perspective can be used to identify differences in perceptions of safety climate among nursing staff. Future studies are needed to identify strategies to improve staff safety attitudes and behaviors. Copyright © 2011 Wolters Kluwer Health | Lippincott Williams & Wilkins

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.)

A feasibility study for Arizona's roadway safety management process using the Highway Safety Manual and SafetyAnalyst : final report.

Science.gov (United States)

2016-07-01

To enable implementation of the American Association of State Highway Transportation (AASHTO) Highway Safety Manual using : SaftetyAnalyst (an AASHTOWare software product), the Arizona Department of Transportation (ADOT) studied the data assessment :...

9 CFR 113.39 - Cat safety tests.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Cat safety tests. 113.39 Section 113... Procedures § 113.39 Cat safety tests. The safety tests provided in this section shall be conducted when... recommended for use in cats. (a) The cat safety test provided in this paragraph shall be used when the Master...

Safety Evaluation of Sclerotium from a Medicinal Mushroom, Lignosus cameronensis (Cultivar: Preclinical Toxicology Studies

Directory of Open Access Journals (Sweden)

Sook-Shien Lee

2017-09-01

Full Text Available Twenty-eight days subacute toxicity studies performed in rats using sclerotial powder of Lignosus cameronensis cultivar was conducted to assess its safety for consumption prior to other scientific investigations on its medicinal benefits, nutraceutical or pharmaceutical application of the mushroom. The study was conducted at 250, 500, and 1000 mg/kg sclerotial powder of L. cameronensis cultivar (n = 5 for each respective dose, on both male and female groups while control groups received only distilled water. At the end of the study (29th day, the animals were sacrificed followed by blood and organs collection for analysis. Subacute toxicity studies done shows that sclerotial powder of L. cameronensis cultivar at 250, 500, and 1000 mg/kg did not induce treatment related changes on behavioral patterns, gross physical appearance, growth pattern, body weight gain, values of hematological and clinical biochemical panels as well as histopathological findings on kidney, spleen, heart, lung and liver of the experimental rats. The no-observed-adverse-effect level dose for sclerotial powder of L. cameronensis cultivar in 28-days sub-acute toxicity study is determined to be 1000 mg/kg.

Safety study of PCC 2140 and ALILOG 21 used as part of safety measurement systems

International Nuclear Information System (INIS)

Meriaux, Pierre; Adnot, Serge; Rayrolles, Catherine.

1978-03-01

The PCC 2140 and ALILOG 21 equipment may be used at C.E.A. or E.D.F., as part of safety measurement systems. In a study of a similar, but earlier equipment, it was noticed that certain types of failures caused the system to switch to the least sensitive measurement range, which was detrimental to safety. This report analyses failure modes leading to unsafe failures and evaluates the risks ran into taking in account tests during use [fr

Fusion Safety Program annual report, fiscal year 1992

International Nuclear Information System (INIS)

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

1993-01-01

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

Airline Safety Management: The development of a proactive safety mechanism model for the evolution of safety management system

OpenAIRE

Hsu, Yueh-Ling

2004-01-01

The systemic origins of many accidents have led to heightened interest in the way in which organisations identify and manage risks within the airline industry. The activities which are thought to represent the term "organisational accident", "safety culture" and "proactive approach" are documented and seek to explain the fact that airlines differ in their willingness and ability to conduct safety management. However, an important but yet relatively undefined task in the airline...

Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

International Nuclear Information System (INIS)

Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

2001-01-01

Safety culture is the perception of each individual and organization of a nuclear power plant that safety is the first priority, and at Tokyo Electric Power Company (TEPCO), we have been practicing it in everyday activities. On the other hand, with the demand for competitiveness of nuclear power becoming even more intense these days, we need to pursue efficient management while maintaining the safety level at the same time. Below, we discuss how to achieve compatibility between safety culture and efficient management as well as enhance safety culture. Discussion at Tepco: safety culture-nurturing activities such as the following are being implemented: 1. informing the employees of the 'Declaration of Safety Promotion' by handing out brochures and posting it on the intranet home page; 2. publishing safety culture reports covering stories on safety culture of other industry sectors, recent movements on safety culture, etc.; 3. conducting periodic questionnaires to employees to grasp how deeply safety culture is being established; 4. carrying out educational programs to learn from past cases inside and outside the nuclear industry; 5. committing to common ownership of information with the public. The current status of safety culture in Japan sometimes seems to be biased to the quest of ultimate safety; rephrasing it, there have been few discussions regarding the sufficiency of the quantitative safety level in conjunction with the safety culture. Safety culture is one of the most crucial foundations guaranteeing the plant's safety, and for example, the plant safety level evaluated by probabilistic safety assessment (PSA) could be said to be valid only on the ground that a sound and sufficient safety culture exists. Although there is no doubt that the safety culture is a fundamental and important attitude of an individual and organization that keeps safety the first priority, the safety culture in itself should not be considered an obstruction to efforts to implement

Conductivity of liquid lithium electrolytes with dispersed mesoporous silica particles

International Nuclear Information System (INIS)

Sann, K.; Roggenbuck, J.; Krawczyk, N.; Buschmann, H.; Luerßen, B.; Fröba, M.; Janek, J.

2012-01-01

Highlights: ► The conductivity of disperse lithium electrolytes with mesoporous fillers is studied. ► In contrast to other investigations in literature, no conductivity enhancement could be observed for standard battery electrolytes and typical mesoporous fillers in various combinations. ► Disperse electrolytes can become relevant in terms of battery safety. ► Dispersions of silicas and electrolyte with LiPF 6 as conducting salt are not stable, although the silicas were dried prior to preparation and the electrolyte water content was controlled. Surface modification of the fillers improved the stability. ► The observed conductivity decrease varied considerably for various fillers. - Abstract: The electrical conductivity of disperse electrolytes was systematically measured as a function of temperature (0 °C to 60 °C) and filler content for different types of fillers with a range of pore geometry, pore structure and specific surface area. As fillers mesoporous silicas SBA-15, MCM-41 and KIT-6 with pore ranges between 3 nm and 15 nm were dispersed in commercially available liquid lithium electrolytes. As electrolytes 1 M of lithium hexafluorophosphate (LiPF 6 ) in a mixture of ethylene carbonate (EC) and diethylene carbonate (DEC) at the ratio 3:7 (wt/wt) and the same solvent mixture with 0.96 M lithium bis(trifluoromethanesulfon)imide (LiTFSI) were used. No conductivity enhancement could be observed, but with respect to safety aspects the highly viscous disperse pastes might be useful. The conductivity decrease varied considerably for the different fillers.

Study on attitudes of students of Islamic Azad University Tehran Medical Branch toward food safety, 2016.

Science.gov (United States)

Miri, Ali; Poursadeghiyan, Mohsen; Baneshi, Mohammad Mehdi; Biglari, Hamed; Yari, Ahmad Reza; Khammar, Alireza

2017-05-01

Given the importance of high-quality healthy food for humans, contamination control is the most important concern for healthy staff. To determine the attitudes of students at Islamic Azad University (Tehran Medical Branch) toward food safety. This cross-sectional and analytic-descriptive study was conducted on 326 students of Azad University of Medical Sciences in 2016. A self-made questionnaire consisting of 40 questions was used. The reliability of the questionnaire was confirmed using internal consistency method (Cronbach's alpha coefficient of 0.80). After collecting data, we use descriptive statistical indexes (mean and standard deviation) among demographic variables and the level of knowledge to describe and analyze the data. The participants' attitudes and operation are measured by Spearman tests, and the analytical results are given using SPSS version 20. According to the findings, 55.3, 30 and 14.7 percent of students had high, moderate and low attitude scores toward food safety, respectively. In addition, male and female students had equal attitudes toward food safety, and no significant relationship between sex and attitude was observed a significant difference (p>0.05), but between educational levels (p=0.008) and ages (p=0.001) of students significance was a positive correlation. Due to the low attitudes score of about half of the students of Islamic Azad University Tehran Medical Branch toward food safety, it can be claimed, food safety training in this community is required.