WorldWideScience

Sample records for agent safety evaluation

  1. NOAC monitoring, reversal agents, and post-approval safety and effectiveness evaluation: A cardiac safety research consortium think tank.

    Science.gov (United States)

    Reiffel, James A; Weitz, Jeffrey I; Reilly, Paul; Kaminskas, Edvardas; Sarich, Troy; Sager, Philip; Seltzer, Jonathan

    2016-07-01

    Four non-vitamin K antagonist oral anticoagulants (dabigatran, rivaroxaban, apixaban, and edoxaban) have been approved in the United States for treatment of atrial fibrillation (AF) and venous thromboembolic disease. They have been as or more effective than the prior standards of care, with less fatal or intracranial bleeding, fewer drug and dietary interactions, and greater patient convenience. Nonetheless, the absence of the ability for clinicians to assess compliance or washout with a simple laboratory test (or to adjust dosing with a similar assessment) and the absence of an antidote to rapidly stop major hemorrhage or to enhance safety in the setting of emergent or urgent surgery/procedures have been limitations to greater non-vitamin K antagonist oral anticoagulant usage and better thromboembolic prevention. Accordingly, a Cardiac Research Safety Consortium "think tank" meeting was held in February 2015 to address these concerns. This manuscript reports on the discussions held and the conclusions reached at that meeting. PMID:27297852

  2. Bioprotective agents in safety control

    Directory of Open Access Journals (Sweden)

    Dimitrijević-Branković Suzana I.

    2003-01-01

    Full Text Available Food poisoning is the one of the main health hazards even today. More than 200 known diseases are transmitted through food. The causes of foodborne illness include viruses, bacteria, parasites, toxins, metals, and prions and the symptoms of foodborne illness range from mild gastroenteritis to life-threatening neurological, hepatic and renal syndromes.The prevention of food poisonings represents very serious task for food manufacturers. Beside food control according to the concept "from the farm to the table" there is increased need for the development of new technology for longer shelf lifes of food. Food fermented by lactic acid bacteria (LAB and traditionally considered to be safe. There are many substances produced by LAB that affect the shelf life of fermented food, by active suppression of poisoning microorganisms growth. Because of that, the LAB is recently considered as bioprotective agents that have important role in food safety.

  3. New Safety rule for Chemical Agents

    CERN Multimedia

    Safety Commission

    2010-01-01

    The following Safety rule has been issued on 08-01-2010: Safety Regulation SR-C Chemical Agents This document applies to all persons under the Director General’s authority. It sets out the minimal requirements for the protection of persons from risks to their safety and health arising, or likely to arise, from the effects of hazardous chemical agents used in any CERN activity. All Safety rules are available on the web pages.

  4. Single-dose safety and pharmacokinetic evaluation of fluorocoxib A: pilot study of novel cyclooxygenase-2-targeted optical imaging agent in a canine model

    Science.gov (United States)

    Cekanova, Maria; Uddin, Md. Jashim; Legendre, Alfred M.; Galyon, Gina; Bartges, Joseph W.; Callens, Amanda; Martin-Jimenez, Tomas; Marnett, Lawrence J.

    2012-11-01

    We evaluated preclinical single-dose safety, pharmacokinetic properties, and specific uptake of the new optical imaging agent fluorocoxib A in dogs. Fluorocoxib A, N-[(5-carboxy-X-rhodaminyl)but-4-yl]-2-[1-(4-chlorobenzoyl)-5-methoxy-2-methyl-1H-indol-3-yl]acetamide, selectively binds and inhibits the cyclooxygenase-2 (COX-2) enzyme, which is overexpressed in many cancers. Safety pilot studies were performed in research dogs following intravenous (i.v.) administration of 0.1 and 1 mg/kg fluorocoxib A. Blood and urine samples collected three days after administration of each dose of fluorocoxib A revealed no evidence of toxicity, and no clinically relevant adverse events were noted on physical examination of exposed dogs over that time period. Pharmacokinetic parameters were assessed in additional research dogs from plasma collected at several time points after i.v. administration of fluorocoxib A using high-performance liquid chromatography analysis. The pharmacokinetic studies using 1 mg/kg showed a peak of fluorocoxib A (92±28 ng/ml) in plasma collected at 0.5 h. Tumor specific uptake of fluorocoxib A was demonstrated using a dog diagnosed with colorectal cancer expressing COX-2. Our data support the safe single-dose administration and in vivo efficacy of fluorocoxib A, suggesting a high potential for successful translation to clinical use as an imaging agent for improved tumor detection in humans.

  5. Phase 2 clinical study of 123I-IBF, a dopamine D2 receptor imaging agent, to evaluate clinical efficacy and safety in Parkinson's disease and Parkinson syndromes

    International Nuclear Information System (INIS)

    A Phase 2 multicenter trial of 123I-IBF, (S)-5-iodo-7-N-[(1-ethyl-2-pyrrolidinyl)methyl] carboxamido-2,3-dihydrobenzofuran, was conducted to evaluate its clinical efficacy and safety in 158 patients with Parkinson's disease (PD) or Parkinson syndromes (PS). SPECT data were acquired at two hours (2H-SPECT), after intravenous injection of 123I-IBF (167 MBq). Additional SPECT scan at three hours (3H-SPECT) and dynamic SPECT scan at most until one hour were performed when possible. No severe side effects due to 123I-IBF injection were observed. The sensitivity, specificity and accuracy for discriminating PS from PD using the striatal specific binding count-to-frontal cortex count ratio (St/Fc-1) in 3H-SPECT were 72.7%, 81.0% and 78.1% in 64 clinically definite cases (i.e., typical cases), respectively. The putamen-to-caudate ratios were significantly lower in striatonigral degeneration compared with those in PD. The contralateral-to-ipsilateral ratios against the symptomatic side of tremor and/or rigidity in the patients with PD (Hoehn and Yahr I) were significantly higher than the left-to-right ratios in the normal controls. St/Fc-1 in 3H-SPECT was significantly lower in the patients showing a poor response to levodopa than in those showing a good response. The dopamine D2 receptor binding potential (k3/k4), obtained by dynamic SPECT based on compartment model analysis, correlated well with the striatal specific binding count-to-occipital cortex count ratio. These results suggest that 123I-IBF is a promising agent for differential diagnosis and pathophysiological evaluation of PD and PS. (author)

  6. Benefit from safety evaluations

    International Nuclear Information System (INIS)

    The uses of the AVR for safety evaluations vary. Fitstly, more than 20 years' operation is a convincing proof of the feasibility and ability of the HTR to function with spherical fuel elements. With regard to an average availability over the years of nearly 70%, it also makes the greatest contribution to operating experience specific to the HTR, which is useful for solidifying the reliability parameters for components surrounded by gas. Also of use for aspects of the safety evaluation are faults which have caused unplanned plant conditions and socalled special events, which total about 150. By far the majority had no safety implications. The three most important events for the aspects dealt with here are: The unintended infeed of a helim/air mixture into the primary circuit via an auxiliary system in May 1971, the fuelling of the reactor with 2400 fuel elements, the faulty state of which was unknown, in 1974, the further feeding of the defective steam-raising unit with the entry of large quantities of water into the reactor in May 1978. (orig.)

  7. Development of an expert system and software agent for aviation safety assessment

    OpenAIRE

    Flowers, Thomas R.; Dowler, David M.

    2000-01-01

    The primary goal of this thesis is to design, develop and test an internet based prototype model for using expert system and software agent technologies to automate some of the analytical tasks in conducting aviation safety assessments using the data collected by the automated Aviation Command Safety Assessment (ACSA) system. The Aviation Command Safety Assessment is a questionnaire survey methodology developed to evaluate a Naval Aviation Command's safety climate, culture, and safety program...

  8. Agent-Based Simulation and Assessment of NAS Security and Safety Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The key innovation proposed here is the use of agent-based modeling and simulation to evaluate the safety of the National Airspace under crisis operations and...

  9. Agent Assignment for Process Management: Pattern Based Agent Performance Evaluation

    Science.gov (United States)

    Jablonski, Stefan; Talib, Ramzan

    In almost all workflow management system the role concept is determined once at the introduction of workflow application and is not reevaluated to observe how successfully certain processes are performed by the authorized agents. This paper describes an approach which evaluates how agents are working successfully and feed this information back for future agent assignment to achieve maximum business benefit for the enterprise. The approach is called Pattern based Agent Performance Evaluation (PAPE) and is based on machine learning technique combined with post processing technique. We report on the result of our experiments and discuss issues and improvement of our approach.

  10. Objectives of safety evaluation

    International Nuclear Information System (INIS)

    An examination of the safety aspects of exported nuclear power plants demonstrates that additional and somewhat special considerations exist for these plants. In view of this and the generally small regulatory staffs of importing coutnries, suggestions are given for measures which should be taken by various organizations involved in the export and import of nuclear power facilities to raise the level of the very essential safety assessment. (orig.)

  11. Experiment to evaluate software safety

    International Nuclear Information System (INIS)

    The process of licensing nuclear power plants for operation consists of mandatory steps featuring detailed examination of the instrumentation and control system by the safety authorities, including softwares. The criticality of these softwares obliges the manufacturer to develop in accordance with the IEC 880 standard 'Computer software in nuclear power plant safety systems' issued by the International Electronic Commission. The evaluation approach, a two-stage assessment is described in detail. In this context, the IPSN (Institute of Protection and Nuclear Safety), the technical support body of the safety authority uses the MALPAS tool to analyse the quality of the programs. (R.P.). 4 refs

  12. LNG Safety Assessment Evaluation Methods

    Energy Technology Data Exchange (ETDEWEB)

    Muna, Alice Baca [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaFleur, Angela Christine [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-05-01

    Sandia National Laboratories evaluated published safety assessment methods across a variety of industries including Liquefied Natural Gas (LNG), hydrogen, land and marine transportation, as well as the US Department of Defense (DOD). All the methods were evaluated for their potential applicability for use in the LNG railroad application. After reviewing the documents included in this report, as well as others not included because of repetition, the Department of Energy (DOE) Hydrogen Safety Plan Checklist is most suitable to be adapted to the LNG railroad application. This report was developed to survey industries related to rail transportation for methodologies and tools that can be used by the FRA to review and evaluate safety assessments submitted by the railroad industry as a part of their implementation plans for liquefied or compressed natural gas storage ( on-board or tender) and engine fueling delivery systems. The main sections of this report provide an overview of various methods found during this survey. In most cases, the reference document is quoted directly. The final section provides discussion and a recommendation for the most appropriate methodology that will allow efficient and consistent evaluations to be made. The DOE Hydrogen Safety Plan Checklist was then revised to adapt it as a methodology for the Federal Railroad Administration’s use in evaluating safety plans submitted by the railroad industry.

  13. EP1000 shutdown safety evaluation

    International Nuclear Information System (INIS)

    The EP1000 uses passive safety systems developed for the AP600 to enhance plant safety and to satisfy EUR requirements. The use of these passive safety systems has provided significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. As a part of the licensing review of the AP600, the US NRC required a systematic assessment of shutdown operations. The NRC reviewed this assessment and concluded that the AP600 is designed to mitigate all design basis events that could occur during shutdown operations and the risk of core damage as a result of an accident that may occur during shutdown operations is acceptably low. A preliminary shutdown safety assessment of the AP1000 has been performed. This assessment included an evaluation of the levels of defense during shutdown operation, an assessment of the design basis events, and evaluation / analysis of these design basis events. Based on this evaluation several shutdown events were identified that were not bounded by events initiating from at-power conditions. These limiting shutdown design basis events were analyzed and based on this analysis, some improvements to the actuation logic have been developed. The results of these analyses demonstrate the capability of the EP1000 passive safety features to provide effective core cooling during shutdown events. (author)

  14. Agent Based Processing of Global Evaluation Function

    CERN Document Server

    Hossain, M Shahriar; Joarder, Md Mahbubul Alam

    2011-01-01

    Load balancing across a networked environment is a monotonous job. Moreover, if the job to be distributed is a constraint satisfying one, the distribution of load demands core intelligence. This paper proposes parallel processing through Global Evaluation Function by means of randomly initialized agents for solving Constraint Satisfaction Problems. A potential issue about the number of agents in a machine under the invocation of distribution is discussed here for securing the maximum benefit from Global Evaluation and parallel processing. The proposed system is compared with typical solution that shows an exclusive outcome supporting the nobility of parallel implementation of Global Evaluation Function with certain number of agents in each invoked machine.

  15. Propagation Modeling of Food Safety Crisis Information Update Based on the Multi-agent System

    OpenAIRE

    Meihong Wu; Jingfei Yang; Zhiling Hong

    2015-01-01

    This study propose a new multi-agent system frame based on epistemic default complex adaptive theory and use the agent based simulation and modeling the information updating process to study food safety crisis information dissemination. Then, we explore interaction effect between each agent in food safety crisis information dissemination at the current environment and mostly reveals how the government agent, food company agent and network media agent influence users confidence in food safety....

  16. Safety evaluation of food flavorings

    International Nuclear Information System (INIS)

    Food flavorings are an essential element in foods. Flavorings are a unique class of food ingredients and excluded from the legislative definition of a food additive because they are regulated by flavor legislation and not food additive legislation. Flavoring ingredients naturally present in foods, have simple chemical structures, low toxicity, and are used in very low levels in foods and beverages resulting in very low levels of human exposure or consumption. Today, the overwhelming regulatory trend is a positive list of flavoring substances, e.g. substances not listed are prohibited. Flavoring substances are added to the list following a safety evaluation based on the conditions of intended use by qualified experts. The basic principles for assessing the safety of flavoring ingredients will be discussed with emphasis on the safety evaluation of flavoring ingredients by the Food and Agriculture Organization (FAO) and World Health Organization (WHO) Joint Expert Committee on Food Additives (JECFA) and the US Flavor and Extract Manufacturers Expert Panel (FEXPAN). The main components of the JECFA evaluation process include chemical structure, human intake (exposure), metabolism to innocuous or harmless substances, and toxicity concerns consistent with JECFA principles. The Flavor and Extract Manufacturers Association (FEMA) evaluation is very similar to the JECFA procedure. Both the JECFA and FEMA evaluation procedures are widely recognized and the results are accepted by many countries. This implies that there is no need for developing countries to conduct their own toxicological assessment of flavoring ingredients unless it is an unique ingredient in one country, but it is helpful to survey intake or exposure assessment. The global safety program established by the International Organization of Flavor Industry (IOFI) resulting in one worldwide open positive list of flavoring substances will be reviewed

  17. Agent-based organizational modelling for analysis of safety culture at an air navigation service provider

    International Nuclear Information System (INIS)

    Assessment of safety culture is done predominantly by questionnaire-based studies, which tend to reveal attitudes on immaterial characteristics (values, beliefs, norms). There is a need for a better understanding of the implications of the material aspects of an organization (structures, processes, etc.) for safety culture and their interactions with the immaterial characteristics. This paper presents a new agent-based organizational modelling approach for integrated and systematic evaluation of material and immaterial characteristics of socio-technical organizations in safety culture analysis. It uniquely considers both the formal organization and the value- and belief-driven behaviour of individuals in the organization. Results are presented of a model for safety occurrence reporting at an air navigation service provider. Model predictions consistent with questionnaire-based results are achieved. A sensitivity analysis provides insight in organizational factors that strongly influence safety culture indicators. The modelling approach can be used in combination with attitude-focused safety culture research, towards an integrated evaluation of material and immaterial characteristics of socio-technical organizations. By using this approach an organization is able to gain a deeper understanding of causes of diverse problems and inefficiencies both in the formal organization and in the behaviour of organizational agents, and to systematically identify and evaluate improvement options.

  18. Probabilistic safety evaluation in Czechoslovakia

    International Nuclear Information System (INIS)

    In connection with the development of Czechoslovak nuclear energetics, probabilistic analyses are also being developed. The event tree method was used in the safety reports of the nuclear power plants with the Soviet pressurized water reactors of the WWER-440 type. The fault tree method has been developed for the analysis of the NPP safety systems. A brief description of systems for the localization of the design basis accident with loss of coolant after the rupture of the main circulation pipe with a diameter of 500 mm (passive system of accumulators, low-pressure injection system of the emergency core cooling system, spray system and bubbling depressurization containment) is presented. These analyses are not accepted as conclusive. Their purpose does not lie in the demonstration of acceptable values of probability of undesirable events with regard to the literary data used and the unspecified limiting criteria. The reliability analyses performed enabled better understanding of the inner connections in various initial failures, better understanding of the safety systems, comparison of alternative solutions, selection of the most significant primary events, a search for common-cause failures, evaluation of the effects of the input reliability data, and optimizing the periodic test rate, etc. The direct simulation Monte Carlo method, incorporated in the SAFEDO-2 code for evaluation of availability or probability of the first failure of repairable complex systems with periodic tests of two groups of components, was used to find the solution. A number of recommendations relating to increasing the reliability of the NPP safety systems have been accepted on the basis of these analyses. (author)

  19. Safety evaluation by living probabilistic safety assessment and safety indicators

    International Nuclear Information System (INIS)

    A continuous monitoring and follow-up of the risks involved in the operation of a nuclear power plant is an important part of the operational safety management. In living probabilistic safety assessment (PSA), the plant specific PSA is applied in daily safety work to support solving of short-term problems, and maintaining as well as enhancing safety in the long term. A quicker and more problem oriented feedback of operating experience can be achieved by well defined safety indicators, highlighting important trends and possible recurrence of operational problems at the plant. Living PSA and safety indicators should be used in combination to effectively support decision making on safety related issues. The Nordic NKS/SIK-1 project also showed how a more systematic and clear basis for such decisions can be formulated by the method of decision analysis. (au) 18 refs

  20. Evaluating safety management system implementation

    International Nuclear Information System (INIS)

    Canada is committed to not only maintaining, but also improving upon our record of having one of the safest aviation systems in the world. The development, implementation and maintenance of safety management systems is a significant step towards improving safety performance. Canada is considered a world leader in this area and we are fully engaged in implementation. By integrating risk management systems and business practices, the aviation industry stands to gain better safety performance with less regulatory intervention. These are important steps towards improving safety and enhancing the public's confidence in the safety of Canada's aviation system. (author)

  1. Antifungal agents for onychomycosis: new treatment strategies to improve safety.

    Science.gov (United States)

    Zane, Lee T; Chanda, Sanjay; Coronado, Dina; Del Rosso, James

    2016-01-01

    Onychomycosis is a common and difficult-to-treat fungal infection of the nail unit that gradually leads to dystrophic changes of the nail plate and nail bed. If untreated, infection progresses and may lead to discomfort, reduced quality of life, and risk of complications in patients with comorbid conditions (eg, diabetes, human immunodeficiency virus, peripheral vascular disease). Onychomycosis treatments are designed to eradicate causative pathogens (most commonly Trichophyton rubrum and Trichophyton mentagrophytes), restore healthy nails, and prevent recurrence or spread of infection. Given the deep-seated nature of most cases of onychomycosis, an effective antifungal agent needs to achieve and maintain sufficient drug concentrations throughout the nail unit for the duration of healthy nail in-growth. Oral antifungal drugs are the most effective available therapy and are generally well tolerated, but may be limited by safety concerns and the potential for drug-drug interactions (DDIs). Thus, treating physicians and pharmacists must be cognizant of a patient's current medications; indeed, it may not be feasible to treat onychomycosis in patients with diabetes, heart disease, or depression because of the risk for DDIs. Current topical therapy is not associated with risk of DDIs. Tavaborole and efinaconazole, two recently approved topical agents, have demonstrated good nail penetration and high negative culture rates in clinical trials of patients with onychomycosis. This article provides the treating physician and pharmacist with information on the safety and effectiveness of current oral (allylamine, azole) and topical (ciclopirox, efinaconazole, tavaborole) treatment to aid in making informed treatment decisions based on the unique characteristics (medication history, comorbidities, nature of onychomycosis) of each patient. PMID:27136621

  2. Status of Nuclear Safety evaluation in China

    Energy Technology Data Exchange (ETDEWEB)

    Tian Jiashu [Technical Integration Division, Beijing Institute of Nuclear Engineering, BJ (China)

    1999-07-01

    Chinese nuclear safety management and control follows international practice, the regulations are mainly from IAEA with the Chinese condition. The regulatory body is National Nuclear Safety Administration (NNSA). The nuclear safety management, surveillance, safety review and evaluation are guided by NNSA with technical support by several units. Beijing Review Center of Nuclear Safety is one of these units, which was founded in 1987 within Beijing Institute of nuclear Engineering (BINE), co-directed by NNSA and BINE, it is the first technical support team to NNSA. Most of the safety reviews and evaluations of Chinese nuclear installations has been finished by this unit. It is described briefly in this paper that the NNSA's main function and organization, regulations on the nuclear safety, procedure of application and issuing of license, the main activities performed by Beijing Review Center of Nuclear Safety, the situation of severe accident analyses in China, etc. (author)

  3. Status of Nuclear Safety evaluation in China

    International Nuclear Information System (INIS)

    Chinese nuclear safety management and control follows international practice, the regulations are mainly from IAEA with the Chinese condition. The regulatory body is National Nuclear Safety Administration (NNSA). The nuclear safety management, surveillance, safety review and evaluation are guided by NNSA with technical support by several units. Beijing Review Center of Nuclear Safety is one of these units, which was founded in 1987 within Beijing Institute of nuclear Engineering (BINE), co-directed by NNSA and BINE, it is the first technical support team to NNSA. Most of the safety reviews and evaluations of Chinese nuclear installations has been finished by this unit. It is described briefly in this paper that the NNSA's main function and organization, regulations on the nuclear safety, procedure of application and issuing of license, the main activities performed by Beijing Review Center of Nuclear Safety, the situation of severe accident analyses in China, etc. (author)

  4. Understanding the relationship between safety investment and safety performance of construction projects through agent-based modeling.

    Science.gov (United States)

    Lu, Miaojia; Cheung, Clara Man; Li, Heng; Hsu, Shu-Chien

    2016-09-01

    The construction industry in Hong Kong increased its safety investment by 300% in the past two decades; however, its accident rate has plateaued to around 50% for one decade. Against this backdrop, researchers have found inconclusive results on the causal relationship between safety investment and safety performance. Using agent-based modeling, this study takes an unconventional bottom-up approach to study safety performance on a construction site as an outcome of a complex system defined by interactions among a worksite, individual construction workers, and different safety investments. Instead of focusing on finding the absolute relationship between safety investment and safety performance, this study contributes to providing a practical framework to investigate how different safety investments interacting with different parameters such as human and environmental factors could affect safety performance. As a result, we could identify cost-effective safety investments under different construction scenarios for delivering optimal safety performance. PMID:27240124

  5. Safety evaluations required in the safety regulations for Monju and the validity confirmation of safety evaluation methods

    International Nuclear Information System (INIS)

    The purposes of this study are to perform the safety evaluations of the fast breeder reactor 'Monju' and to confirm the validity of the safety evaluation methods. In JFY 2012, the following results were obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes, such as a core damage analysis code, were carried out according to the plan. 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)

  6. Efficacy and Safety of Novel Anticoagulants Compared with Established Agents

    OpenAIRE

    Rybak, Iwona; Ehle, Michael; Buckley, Leo; Fanikos, John

    2011-01-01

    Dabigatran, rivaroxaban, and apixaban are novel oral anticoagulants that offer major advantages over existing agents. The onset of the anticoagulant effect of these agents is rapid. Each agent has a predictable anticoagulant response that eliminates the need for monitoring. Clinical trials have been completed with all three agents in the prevention and treatment of the three leading causes of cardiovascular death: myocardial infarction, stroke, and venous thromboembolism (VTE). Novel agents h...

  7. Contrasting safety assessments of a runway incursion scenario: Event sequence analysis versus multi-agent dynamic risk modelling

    International Nuclear Information System (INIS)

    In the safety literature it has been argued, that in a complex socio-technical system safety cannot be well analysed by event sequence based approaches, but requires to capture the complex interactions and performance variability of the socio-technical system. In order to evaluate the quantitative and practical consequences of these arguments, this study compares two approaches to assess accident risk of an example safety critical sociotechnical system. It contrasts an event sequence based assessment with a multi-agent dynamic risk model (MA-DRM) based assessment, both of which are performed for a particular runway incursion scenario. The event sequence analysis uses the well-known event tree modelling formalism and the MA-DRM based approach combines agent based modelling, hybrid Petri nets and rare event Monte Carlo simulation. The comparison addresses qualitative and quantitative differences in the methods, attained risk levels, and in the prime factors influencing the safety of the operation. The assessments show considerable differences in the accident risk implications of the performance of human operators and technical systems in the runway incursion scenario. In contrast with the event sequence based results, the MA-DRM based results show that the accident risk is not manifest from the performance of and relations between individual human operators and technical systems. Instead, the safety risk emerges from the totality of the performance and interactions in the agent based model of the safety critical operation considered, which coincides very well with the argumentation in the safety literature.

  8. Evaluating Reputation Systems for Agent Mediated e-Commerce

    OpenAIRE

    Gaur, Vibha; Sharma, Neeraj Kumar; Bedi, Punam

    2013-01-01

    Agent mediated e-commerce involves buying and selling on Internet through software agents. The success of an agent mediated e-commerce system lies in the underlying reputation management system which is used to improve the quality of services in e-market environment. A reputation system encourages the honest behaviour of seller agents and discourages the malicious behaviour of dishonest seller agents in the e-market where actual traders never meet each other. This paper evaluates various repu...

  9. Site Evaluation for Nuclear Installations. Safety Requirements

    International Nuclear Information System (INIS)

    This publication establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references section provide recommendations on how to meet the requirements established in this publication. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

  10. Subjective performance evaluations and reciprocity in principal-agent relations

    DEFF Research Database (Denmark)

    Sebald, Alexander Christopher; Walzl, Markus

    2014-01-01

    We conduct a laboratory experiment with agents working on, and principals benefiting from, a real effort task in which the agents' performance can only be evaluated subjectively. Principals give subjective performance feedback to agents, and agents have an opportunity to sanction principals. In...... contrast to existing models of reciprocity, we find that agents tend to sanction whenever the feedback of principals is below their subjective self-evaluations even if agents' pay-offs are independent of it. In turn, principals provide more positive feedback (relative to their actual performance assessment...

  11. Experiment on safety software evaluation

    International Nuclear Information System (INIS)

    The licensing procedures process of nuclear plants includes compulsory steps which bring about a thorough exam of the commands control system. In this context the IPSN uses a tool called MALPAS to carry out an analysis of the quality of the software involved in safety control. The IPSN also try to obtain the automation of the generation of test games necessary for dynamical analysis. The MALPAS tool puts forward the particularities of programing which can influence the testability and the upholding of the studied software. (TEC). 4 refs

  12. Plutonium Finishing Plant safety evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    1995-01-01

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

  13. Plutonium Finishing Plant safety evaluation report

    International Nuclear Information System (INIS)

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE's independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91

  14. Squale: evaluation criteria of functioning safety

    International Nuclear Information System (INIS)

    The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.)

  15. Safety evaluation of large ventilation networks

    International Nuclear Information System (INIS)

    For large ventilation networks, it is necessary to make a safety evaluation of their responses to perturbations such as blower failure, unexpected transfers, local pressurization. This evaluation is not easy to perform because of the many interrelationships between the different parts of the networks, interrelationships coming from the circulations of workers and matetials between cells and rooms and from the usefulness of air transfers through zones of different classifications. This evaluation is all the more necessary since new imperatives in energy savings push for minimizing the air flows, which tends to render the network more sensitive to perturbations. A program to evaluate safety has been developed by the Service de Protection Technique in cooperation with operators and designers of big nuclear facilities and the first applications presented here show the weak points of the installation studied from the safety view point

  16. Safety evaluation of synthetic β-carotene

    NARCIS (Netherlands)

    Woutersen, R.A.; Wolterbeek, A.P.M.; Appel, M.J.; Berg, H. van den; Goldbohm, R.A.; Feron, V.J.

    1999-01-01

    The safety of β-carotene was reassessed by evaluating the relevant literature on the beneficial and adverse effects of β-carotene on cancer and, in particular, by evaluating the results of toxicity studies. β- Carotene appeared neither genotoxic nor reprotoxic or teratogenic, and no signs of organ t

  17. THE STUDY THE EFFICACY AND SAFETY OF ANTIMICROBIAL AGENTS

    Directory of Open Access Journals (Sweden)

    V. V. Bagaeva

    2015-01-01

    Full Text Available Abstract:Effective treatment of patients with infectious and inflammatory diseases of the skin and mucous membranes often involves the use of antimicrobial agents.The purpose of the study was an in vitro estimation of cytotoxicity and the efficiency of national resources for local use: gel with bacteriophages («Otofag», «Fagogin», «Fagoderm», «Fagodent» and antiseptic — «Сhlorhexidine» and «Miramistin».Materials and Methods. To study the effectiveness of antimicrobial agents they used to provide crop strains of Staphylococcus aureus and Streptococcus pyogenes as one of the most common representatives of pathogens. The study of cell viability and cytotoxicity antimicrobials performed on cell lines KB — epidermoid carcinoma of the oral cavity of a human. For this purpose we use mikrotetrazoly test, which is widely used in the assessment of the effects on the cells of toxins, pharmaceuticals, adverse environmental factors, allowing to evaluate the toxicity of investigational drugs in vitro.The results showed that the efficacy against pathogens Staphylococcus aureus and Streptococcus pyogenes, has even a 10‑fold dilution of «Сhlorhexidine» 0.05% and gels with bacteriophages. Antiseptic «Miramistin» is effective only on the initial concentration. The study of cytotoxicity showed that the processing of epidermoid carcinoma cells with «Chlorhexidine» and «Мiramistin» invokes the irreversible reactions, while the composition processing of gels based on bacteriophages not further affect cell viability.Conclusions The results of the experiment confirmed the significant toxicity of tools such as «Сhlorhexidine» and «Miramistin» in proposed concentrations in the pharmacy network. Despite the high efficiency of these vehicles with regard to the studied pathogens, their long-term use in treatment of inflammatory diseases of the skin and mucous membranes can cause a slowing of repair processes. Gel means with bacteriophages

  18. Micromorphological Evaluation of Dentin Treated with Different Desensitizing Agents

    OpenAIRE

    2013-01-01

    Introduction: The purpose of a desensitizing agent is a permanent coating or filling of dentin surface. Morphological analysis in vitro of this treated surface is essential to understand the interaction between desensitizing agent and hypersensitive dentin. The aim was to evaluate the morphology of four dentin surface treated with desensitizing agents.

  19. The Interagency Nuclear Safety Review Panel's Galileo safety evaluation report

    International Nuclear Information System (INIS)

    The safety evaluation report (SER) for Galileo was prepared by the Interagency Nuclear Safety Review Panel (INSRP) coordinators in accordance with Presidential directive/National Security Council memorandum 25. The INSRP consists of three coordinators appointed by their respective agencies, the Department of Defense, the Department of Energy (DOE), and the National Aeronautics and Space Administration (NASA). These individuals are independent of the program being evaluated and depend on independent experts drawn from the national technical community to serve on the five INSRP subpanels. The Galileo SER is based on input provided by the NASA Galileo Program Office, review and assessment of the final safety analysis report prepared by the Office of Special Applications of the DOE under a memorandum of understanding between NASA and the DOE, as well as other related data and analyses. The SER was prepared for use by the agencies and the Office of Science and Technology Policy, Executive Office of the Present for use in their launch decision-making process. Although more than 20 nuclear-powered space missions have been previously reviewed via the INSRP process, the Galileo review constituted the first review of a nuclear power source associated with launch aboard the Space Transportation System

  20. Drug Safety Communication: Erythropoiesis-Stimulating Agents (ESAs)

    Science.gov (United States)

    ... Health and Human Services FDA U.S. Food and Drug Administration Protecting and Promoting Your Health A to ... it was archived. Search Archive Submit archive search Drugs Home Drugs Drug Safety and Availability Postmarket Drug ...

  1. Evaluation of tank data for safety screening

    International Nuclear Information System (INIS)

    This document presents the evaluation of the adequacy of the sampling and analysis of Hanford tank wastes for safety screening. A comparison was made of the data collected through sampling and analysis to the data required by the Safety Screening Data Quality Objective (DQO) (Dukelow et al. 1995). The evaluation was for the purpose of determining whether the sampling met the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 93-5 Implementation Plan milestone 5.6.3.13. Milestone 5.6.3.13 states, ''Core sample all tanks by 2002'' (DOE-RL 1996). The milestone is considered completed for a specific tank if sufficient sample material was taken and analyzed to meet the Safety Screening DQO. A description of the scope is presented in Section 2.0. The definition of Safety Screening DQO needs is presented in Section 3.0. The logic used to determine if the sampling and analysis was sufficient is presented in Section 4.0. In Section 5.0, the tanks that satisfy the Safety Screening DQO are presented. In total, 138 tanks were identified as having been sampled since 1989, and 132 of those tanks met the established criteria. Six tanks did not meet the established criteria. Section 6.0 lists the 45 tanks that either did not meet the criteria or were not sampled since 1989

  2. Research on the effect estimation of seismic safety evaluation

    Institute of Scientific and Technical Information of China (English)

    邹其嘉; 陶裕禄

    2004-01-01

    Seismic safety evaluation is a basic work for determining the seismic resistance requirements of major construction projects. The effect, especially the economic effect of the seismic safety evaluation has been generally concerned. The paper gives a model for estimating the effect of seismic safety evaluation and calculates roughly the economic effect of seismic safety evaluation with some examples.

  3. Evaluating the safety of irradiated foods

    International Nuclear Information System (INIS)

    Health agencies throughout the world have evaluated the safety of irradiated foods by considering the likelihood that irradiation would induce radioactivity, produce toxic radiolytic products, destroy nutrients, or change the microbiological profile of organisms in the food. After years of study, researchers have concluded that foods irradiated under the proper conditions will not produce adverse health effects when consumed

  4. Design and evaluation of explainable BDI agents

    NARCIS (Netherlands)

    Harbers, M.; Bosch, K. van den; Meyer, J.J.C.

    2010-01-01

    It is widely acknowledged that providing explanations is an important capability of intelligent systems. Explanation capabilities are useful, for example, in scenario-based training systems with intelligent virtual agents. Trainees learn more from scenario-based training when they understand why the

  5. Evaluation of safety margins of operating reactors

    International Nuclear Information System (INIS)

    The margins to acceptance criteria have been determined by conservative evaluation model calculations in the past. During the recent years an increasing interest in computational reactor safety analysis is to replace these conservative calculations by 'best estimate' calculations supplemented by uncertainty analysis of the code results. Safety margin of operating reactors is defined as the difference in physical units between the critical value of an assigned parameter associated with the failure of a system or component or with a phenomenon and the actual value of that parameter. The most important safety margins relate to physical barriers against release of radioactive material. Margin can be increased by improving analytical methods or plant equipment. Once this increased margin is identified, some of the increase can be used to improve plant performance. Computer code calculations are used to assess the values of safety margins. For this purpose a best estimate or conservative calculation is used. In case of best estimate calculation it is necessary to determine the uncertainty band when determining the safety margin. A prerequisite for this approach is, however, that qualified computer codes are available which are validated by pre- and post-test calculations of appropriate experiments. Utilities intend to minimise the cost of production and to maximise outputs of the operating plants. These goals can be achieved by technical measures, such as power up-rating, increase of maximum fuel linear heat generation rate, optimisation of fuel management with the use of high burn-ups, use of mixed (i.e. U and Pu) oxide (MOX) fuel or use of mixed cores. Such plant modifications require an in-depth safety analysis to evaluate the possible safety impact. The analysis has to consider all the consequences of the plant modifications with respect to the margins existing. The analysis must consider the core characteristics and the plant behaviour, taking into account the

  6. Nuclear safety culture evaluation model based on SSE-CMM

    International Nuclear Information System (INIS)

    Safety culture, which is of great significance to establish safety objectives, characterizes level of enterprise safety production and development. Traditional safety culture evaluation models emphasis on thinking and behavior of individual and organization, and pay attention to evaluation results while ignore process. Moreover, determining evaluation indicators lacks objective evidence. A novel multidimensional safety culture evaluation model, which has scientific and completeness, is addressed by building an preliminary mapping between safety culture and SSE-CMM's (Systems Security Engineering Capability Maturity Model) process area and generic practice. The model focuses on enterprise system security engineering process evaluation and provides new ideas and scientific evidences for the study of safety culture. (authors)

  7. [Weighing use and safety of therapeutic agents and feed additives (author's transl)].

    Science.gov (United States)

    van der Wal, P

    1982-02-01

    (1) The pros and cons of using feed additives and therapeutic agents may be successfully weighed in the light of carefully considered consumer requirements. (2) The socio-economic interests of the producer and the welfare of the animal will also determine the response of the production apparatus to consumer requirements. (3) Consumption of the current amounts of products of animal origin and maintenance of price and quality will only be feasible in the event of rational large-scale production in which constituents used in nutrition, prophylaxis and therapeutics are highly important factors. (4) Using these ingredients should be preceded by accurate evaluation of their use and safety. Testing facilities, conduct of studies and reporting should be such as to make the results nationally and internationally acceptable to all those concerned. (5) In deciding whether feed constituents are acceptable in view of the established use and safety, compliance will have to be sought with those standards which are accepted in other fields of society. Measures which result in raising the price of food without actually helping to reduce the risks to the safety of man, animals and environment, are likely to be rejected by any well-informed consumer who is aware of the facts. (6) For accurate weighing of use and safety at a national level, possibilities are hardly adequate in Europe. Decisions reached within the framework of the European Community, also tuned to U.S.A.- conditions are rightly encouraged. A centrally managed professionally staffed and equipped test system in the European Community would appear to be indispensable. PMID:7058519

  8. An evaluation of proximal surface cleansing agents.

    Science.gov (United States)

    Wolffe, G N

    1976-08-01

    The effectiveness of the Interspace brush, Inter-Dens, and waxed dental floss as proximal surface cleansing agents was compared in 35 subjects. Each subject used all three methods of cleansing in random order of selection. Statistical analysis of the results showed that there was no difference in the effectiveness of any one of these three agents. However, proximal surfaces of anterior teeth where cleaned more effectively than posterior teeth. The coronal half of the proximal surfaces was cleaned more effectively than the apical half and the facial half more effectively than the lingual half when Inter-Dens was used. Comparison of cleansing effectiveness between facial and lingual halves of proximal surfaces for the Interspace brush and waxed dental floss showed no significant difference. Mesial and distal proximal surfaces were cleaned with similar effectiveness. Plaque control was only satisfactory on approximately half of the proximal surfaces, though a wide variation occurred. Significantly lower plaque scores were found 1 week after the initial instruction session, irrespective of the agent used. The majority of subjects preferred Inter-Dens whilst waxed dental floss was the least-liked method of cleansing. PMID:1067276

  9. MODEL-BASED PERFORMANCE EVALUATION APPROACH FOR MOBILE AGENT SYSTEMS

    Institute of Scientific and Technical Information of China (English)

    Li Xin; Mi Zhengkun; Meng Xudong

    2004-01-01

    Claimed as the next generation programming paradigm, mobile agent technology has attracted extensive interests in recent years. However, up to now, limited research efforts have been devoted to the performance study of mobile agent system and most of these researches focus on agent behavior analysis resulting in that models are hard to apply to mobile agent systems. To bridge the gap, a new performance evaluation model derived from operation mechanisms of mobile agent platforms is proposed. Details are discussed for the design of companion simulation software, which can provide the system performance such as response time of platform to mobile agent. Further investigation is followed on the determination of model parameters. Finally comparison is made between the model-based simulation results and measurement-based real performance of mobile agent systems. The results show that the proposed model and designed software are effective in evaluating performance characteristics of mobile agent systems. The proposed approach can also be considered as the basis of performance analysis for large systems composed of multiple mobile agent platforms.

  10. Safety of Gadoterate Meglumine (Gd-DOTA) as a Contrast Agent for Magnetic Resonance Imaging

    OpenAIRE

    Ishiguchi, Tsuneo; Takahashi, Shoki

    2012-01-01

    Background: Safety is a primary concern with contrast agents used for MRI. If precautions could be taken before the repeated administration of gadolinium-based contrast media, then the awareness and management of adverse reactions would be more efficient. Objectives: To assess the safety and efficacy of gadoterate meglumine (Gd-DOTA) [Magnescope® in Japan, Dotarem® in other countries], a gadolinium-based contrast agent, in patients undergoing imaging of the brain/spinal cord and/or trunk/limb...

  11. A probabilistic bridge safety evaluation against floods.

    Science.gov (United States)

    Liao, Kuo-Wei; Muto, Yasunori; Chen, Wei-Lun; Wu, Bang-Ho

    2016-01-01

    To further capture the influences of uncertain factors on river bridge safety evaluation, a probabilistic approach is adopted. Because this is a systematic and nonlinear problem, MPP-based reliability analyses are not suitable. A sampling approach such as a Monte Carlo simulation (MCS) or importance sampling is often adopted. To enhance the efficiency of the sampling approach, this study utilizes Bayesian least squares support vector machines to construct a response surface followed by an MCS, providing a more precise safety index. Although there are several factors impacting the flood-resistant reliability of a bridge, previous experiences and studies show that the reliability of the bridge itself plays a key role. Thus, the goal of this study is to analyze the system reliability of a selected bridge that includes five limit states. The random variables considered here include the water surface elevation, water velocity, local scour depth, soil property and wind load. Because the first three variables are deeply affected by river hydraulics, a probabilistic HEC-RAS-based simulation is performed to capture the uncertainties in those random variables. The accuracy and variation of our solutions are confirmed by a direct MCS to ensure the applicability of the proposed approach. The results of a numerical example indicate that the proposed approach can efficiently provide an accurate bridge safety evaluation and maintain satisfactory variation. PMID:27386269

  12. Preclosure radiological safety evaluation: Exploratory Studies Facility

    International Nuclear Information System (INIS)

    A radiological safety evaluation is performed to determine the impacts of Exploratory Studies Facility (ESF) design changes on the preclosure public radiological safety for a potential nuclear waste repository at Yucca Mountain, Nevada. Although the ESF design has undergone significant modification, incorporation of the modified design requires only modest changes to the conceptual repository configuration. To the extent feasible, the results of earlier safety evaluations presented in SAND84-2641, SAND88-7061, and SAND89-7024, which were based on the original ESF configuration, are compared with the results for the modified configuration. This comparison provides an estimate of the range of analysis uncertainty. This preliminary analysis indicates that there are no Q-scenarios, which are defined as those scenarios with a net occurrence probability of greater than 10-6/yr and produce a radiological dose at the 5-km controlled area boundary of greater than 0.5 rem. The analysis yielded estimates for an underground accident of a probability of 3.8 x 10-15/yr and a dose of 1.5 rem. For a surface-initiated accident, a probability of 1.5 x 10-12/yr and a dose of 0.6 rem was estimated

  13. Safety evaluation of encapsulated vitrified products, (1)

    International Nuclear Information System (INIS)

    The steady state heat flow method was studied to establish a thermal conductivity measuring method for vitrified HLW in a canister. Thermal conductivity of encapsulated borosilicate glass with simulated HLW was measured between 350 and 7500C with different contents up to 25 wt%. The thermal conductivity increased abruptly near 7000C. The thermal conductivity had a maximum for about 6 wt% of the waste content. Above 6000C, the thermal conductivity decreased for waste contents beyond 10 wt%. Below 5000C, the thermal conductivity increased for waste contents beyond 10 wt%. Assuming the central and the surface temperature of HLW glass product to be 500 and 3500C respectively, the surface area per gramme waste calculated is smaller as the concentration. The leachability must be high at very high concentration of the waste, so that there will be an optimal concentration for the safety. From the leachability, the thermal conductivity in overall safety evaluation was examined. (author)

  14. Evaluation of antitussive agents in man.

    Science.gov (United States)

    Parvez, L; Vaidya, M; Sakhardande, A; Subburaj, S; Rajagopalan, T G

    1996-01-01

    Methodology to evaluate the efficacy of antitussive drugs rely largely on subjective methods and cough counts. There are few studies in cough due to natural disease especially using objective techniques. This paper presents data from a series of randomized, double blind, placebo controlled clinical trials in cough due to both chronic bronchopulmonary disease and acute upper respiratory tract infections. In these studies, cough was quantified using a standardized and validated computerized system for the acquisition and multidimensional analysis of the cough sound. Key objective parameters like cough counts, intensity, latency and total effort expended were studied. Guaiphenesin and bromhexine showed significant expectorant effects in patients with productive cough due to chronic bronchopulmonary disease. Differences were observed in speed of action, and objective and subjective measures, that probably indicate differences in drug action. More recently, three studies evaluated the antitussive drug dextromethorphan in non-productive cough due to uncomplicated upper respiratory tract infections. Reproducible cough suppressant effects were demonstrated after a single 30 mg dose using objective measures of cough counts, latency and total effort. These results establish the sensitivity and robustness of the cough quantitation methodology in the objective evaluation of cough treatments. PMID:9232667

  15. Safety evaluation for packaging (onsite) SERF cask

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, W.S.

    1997-10-24

    This safety evaluation for packaging (SEP) documents the ability of the Special Environmental Radiometallurgy Facility (SERF) Cask to meet the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B quantities (up to highway route controlled quantities) of radioactive material within the 300 Area of the Hanford Site. This document shall be used to ensure that loading, tie down, transport, and unloading of the SERF Cask are performed in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required.

  16. Safety evaluation for packaging (onsite) SERF cask

    International Nuclear Information System (INIS)

    This safety evaluation for packaging (SEP) documents the ability of the Special Environmental Radiometallurgy Facility (SERF) Cask to meet the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B quantities (up to highway route controlled quantities) of radioactive material within the 300 Area of the Hanford Site. This document shall be used to ensure that loading, tie down, transport, and unloading of the SERF Cask are performed in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required

  17. Safety assessment of new antithrombotic agents: lessons from the EXTEND study on ximelagatran

    DEFF Research Database (Denmark)

    Agnelli, G; Eriksson, B I; Cohen, A T;

    2009-01-01

    BACKGROUND: Ximelagatran, the first oral direct thrombin inhibitor, was shown to be an effective antithrombotic agent but was associated with potential liver toxicity after prolonged administration. OBJECTIVES AND METHODS: The aim of the EXTEND study was to assess safety and efficacy of extended ...

  18. Safety Evaluation of the EVOLVE Blanket Concept

    International Nuclear Information System (INIS)

    This article summarizes the results of the safety evaluation of the Evaporation of Lithium and Vapor Extraction (EVOLVE) W-alloy first wall (FW) and blanket concept. We have analyzed the EVOLVE design response during a confinement bypass accident. A confinement bypass accident was chosen because, based on previous safety studies, this accident can produce environmental releases by breaching the primary radioactive confinement boundary of EVOLVE, which is the EVOLVE vacuum vessel (VV). As a consequence of a bypass accident, air from a room adjoining the reactor enters the plasma chamber by way of a failed VV port. This air reacts with the high temperature metals inside of the VV to release energy in the case of a lithium spill, or to mobilize radioactive material by oxidation, and then transport this material to the environment by natural convection airflow through the failed VV port. We use the MELCOR code to analyze the response of EVOLVE during this accident. Based on these results, the EVOLVE concept can meet the no-evacuation dose goal set by the DOE Fusion Safety Standard if the EVOLVE confinement building ventilation system is closed within two hours of the onset of this accident

  19. Safety evaluation for packaging CPC metal boxes

    International Nuclear Information System (INIS)

    This Safety Evaluation for Packaging (SEP) provides authorization for the use of Container Products Corporation (CPC) metal boxes, as described in this document, for the interarea shipment of radioactive contaminated equipment and debris for storage in the Central Waste Complex (CWC) or T Plant located in the 200 West Area. Authorization is granted until November 30, 1995. The CPC boxes included in this SEP were originally procured as US Department of Transportation (DOT) Specification 7A Type A boxes. A review of the documentation provided by the manufacturer revealed the documentation did not adequately demonstrate compliance to the 4 ft drop test requirement of 49 CFR 173.465(c). Preparation of a SEP is necessary to document the equivalent safety of the onsite shipment in lieu of meeting DOT packaging requirements until adequate documentation is received. The equivalent safety of the shipment is based on the fact that the radioactive contents consist of contaminated equipment and debris which are not dispersible. Each piece is wrapped in two layers of no less than 4 mil plastic prior to being placed in the box which has an additional 10 mil liner. Pointed objects and sharp edges are padded to prevent puncture of the plastic liner and wrapping

  20. Preliminary safety evaluation for CSR1000 with passive safety system

    International Nuclear Information System (INIS)

    Highlights: • The basic information of a Chinese SCWR concept CSR1000 is introduced. • An innovative passive safety system is proposed for CSR1000. • 6 Transients and 3 accidents are analysed with system code SCTRAN. • The passive safety systems greatly mitigate the consequences of these incidents. • The inherent safety of CSR1000 is enhanced. - Abstract: This paper describes the preliminary safety analysis of the Chinese Supercritical water cooled Reactor (CSR1000), which is proposed by Nuclear Power Institute of China (NPIC). The two-pass core design applied to CSR1000 decreases the fuel cladding temperature and flattens the power distribution of the core at normal operation condition. Each fuel assembly is made up of four sub-assemblies with downward-flow water rods, which is favorable to the core cooling during abnormal conditions due to the large water inventory of the water rods. Additionally, a passive safety system is proposed for CSR1000 to increase the safety reliability at abnormal conditions. In this paper, accidents of “pump seizure”, “loss of coolant flow accidents (LOFA)”, “core depressurization”, as well as some typical transients are analysed with code SCTRAN, which is a one-dimensional safety analysis code for SCWRs. The results indicate that the maximum cladding surface temperatures (MCST), which is the most important safety criterion, of the both passes in the mentioned incidents are all below the safety criterion by a large margin. The sensitivity analyses of the delay time of RCPs trip in “loss of offsite power” and the delay time of RMT actuation in “loss of coolant flowrate” were also included in this paper. The analyses have shown that the core design of CSR1000 is feasible and the proposed passive safety system is capable of mitigating the consequences of the selected abnormalities

  1. A Methodology for Evaluating Quantitative Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

    Through several accidents of NPPs including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, nuclear safety culture has been emphasized in reactor safety world-widely. In Korea, KHNP evaluates the safety culture of NPP itself. KHNP developed the principles of the safety culture in consideration of the international standards. A questionnaire and interview questions are also developed based on these principles and it is used for evaluating the safety culture. However, existing methodology to evaluate the safety culture has some disadvantages. First, it is difficult to maintain the consistency of the assessment. Second, the period of safety culture assessment is too long (every two years) so it has limitations in preventing accidents occurred by a lack of safety culture. Third, it is not possible to measure the change in the risk of NPPs by weak safety culture since it is not clearly explains the effect of safety culture on the safety of NPPs. In this study, Safety Culture Impact Assessment Model (SCIAM) is developed overcoming these disadvantages. In this study, SCIAM which overcoming disadvantages of exiting safety culture assessment method is developed. SCIAM uses SCII to monitor the statues of the safety culture periodically and also uses RCDF to quantify the safety culture impact on NPP's safety. It is significant that SCIAM represents the standard of the healthy nuclear safety culture, while the exiting safety culture assessment presented only vulnerability of the safety culture of organization. SCIAM might contribute to monitoring the level of safety culture periodically and, to improving the safety of NPP.

  2. Evaluation of residue drum storage safety risks

    International Nuclear Information System (INIS)

    A study was conducted to determine if any potential safety problems exist in the residue drum backlog at the Rocky Flats Plant. Plutonium residues stored in 55-gallon drums were packaged for short-term storage until the residues could be processed for plutonium recovery. These residues have now been determined by the Department of Energy to be waste materials, and the residues will remain in storage until plans for disposal of the material can be developed. The packaging configurations which were safe for short-term storage may not be safe for long-term storage. Interviews with Rocky Flats personnel involved with packaging the residues reveal that more than one packaging configuration was used for some of the residues. A tabulation of packaging configurations was developed based on the information obtained from the interviews. A number of potential safety problems were identified during this study, including hydrogen generation from some residues and residue packaging materials, contamination containment loss, metal residue packaging container corrosion, and pyrophoric plutonium compound formation. Risk factors were developed for evaluating the risk potential of the various residue categories, and the residues in storage at Rocky Flats were ranked by risk potential. Preliminary drum head space gas sampling studies have demonstrated the potential for formation of flammable hydrogen-oxygen mixtures in some residue drums

  3. Systematic safety evaluation on photoluminescent carbon dots

    Science.gov (United States)

    Wang, Kan; Gao, Zhongcai; Gao, Guo; Wo, Yan; Wang, Yuxia; Shen, Guangxia; Cui, Daxiang

    2013-03-01

    Photoluminescent carbon dots (C-dots) were prepared using the improved nitric acid oxidation method. The C-dots were characterized by tapping-mode atomic force microscopy, and UV-vis absorption spectroscopy. The C-dots were subjected to systematic safety evaluation via acute toxicity, subacute toxicity, and genotoxicity experiments (including mouse bone marrow micronuclear test and Salmonella typhimurium mutagenicity test). The results showed that the C-dots were successfully prepared with good stability, high dispersibility, and water solubility. At all studied C-dot dosages, no significant toxic effect, i.e., no abnormality or lesion, was observed in the organs of the animals. Therefore, the C-dots are non-toxic to mice under any dose and have potential use in fluorescence imaging in vivo, tumor cell tracking, and others.

  4. Applications of integrated safety analysis methodology to reload safety evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Chan Su; Um, Kil Sup [Korea Nuclear Fuel, Daejeon (Korea, Republic of)

    2011-03-15

    Korea Nuclear Fuel is developing the X-GEN fuel which shows high performance and robust reliability for the worldwide supply. However, the simplified code systems such as CESEC-III which were developed in 1970s are still used in the current Non-LOCA safety analysis of OPR1000 and APR1400 plants. Therefore, it is essential to secure an advanced safety analysis methodology to make the best use of the merits of X-GEN fuel. To accomplish this purpose, the integrated safety analysis methodology (iSAM), is developed by selecting the best-estimate thermal-hydraulic code RETRAN. iSAM possesses remarkable advantages, such as generality, integrity, and designer-friendly features. That is, iSAM can be applied to both OPR1000 and APR1400 plants and uses only one computer code, RETRAN, in the whole scope of the non-LOCA safety analyses. Also the iSAM adopts the unique and automatic initialization and run tool, automatic steady-state initialization and safety analysis tool (ASSIST), to enable unhandy designers to use the new design code RETRAN without difficulty. In this paper, a brief overview of the iSAM is given, and the results of applying the iSAM to typical non-LOCA transients being checked during the reload design are reported. The typical non-LOCA transients selected are the single control element assembly withdrawal (SCEAW) accident, the asymmetric steam generator transients (ASGT), the locked rotor (LR) accident, and bank CEA withdrawal (BCEAW) event. Comparison to current licensing results shows a close resemblance; thus, it reveals that the iSAM can be applied to the non-LOCA safety analysis of OPR1000 and APR1400 plants

  5. Applications of integrated safety analysis methodology to reload safety evaluation

    International Nuclear Information System (INIS)

    Korea Nuclear Fuel is developing the X-GEN fuel which shows high performance and robust reliability for the worldwide supply. However, the simplified code systems such as CESEC-III which were developed in 1970s are still used in the current Non-LOCA safety analysis of OPR1000 and APR1400 plants. Therefore, it is essential to secure an advanced safety analysis methodology to make the best use of the merits of X-GEN fuel. To accomplish this purpose, the integrated safety analysis methodology (iSAM), is developed by selecting the best-estimate thermal-hydraulic code RETRAN. iSAM possesses remarkable advantages, such as generality, integrity, and designer-friendly features. That is, iSAM can be applied to both OPR1000 and APR1400 plants and uses only one computer code, RETRAN, in the whole scope of the non-LOCA safety analyses. Also the iSAM adopts the unique and automatic initialization and run tool, automatic steady-state initialization and safety analysis tool (ASSIST), to enable unhandy designers to use the new design code RETRAN without difficulty. In this paper, a brief overview of the iSAM is given, and the results of applying the iSAM to typical non-LOCA transients being checked during the reload design are reported. The typical non-LOCA transients selected are the single control element assembly withdrawal (SCEAW) accident, the asymmetric steam generator transients (ASGT), the locked rotor (LR) accident, and bank CEA withdrawal (BCEAW) event. Comparison to current licensing results shows a close resemblance; thus, it reveals that the iSAM can be applied to the non-LOCA safety analysis of OPR1000 and APR1400 plants

  6. Evaluation of closed-loop performance of an estimation strategy for decentralized safety controller under communication delay and measurement uncertainty

    OpenAIRE

    Bresch-Pietri, Delphine; Del Vecchio, Domitilla

    2015-01-01

    We present here the details of the evaluation performance of an estimation strategy for a decentralized safety controller for two agents, subject to communication delay and imperfect measurements. The control objective is to ensure safety, meaning that the state of the two-agent system does not enter an undesired set in the state space. Assuming that we know a feedback map designed for the delay-free case, we propose a state estimation strategy which guarantees control agreement between the t...

  7. Note on evaluating safety performance of road infrastructure to motivate safety competition.

    Science.gov (United States)

    Han, Sangjin

    2016-01-01

    Road infrastructures are usually developed and maintained by governments or public sectors. There is no competitor in the market of their jurisdiction. This monopolic feature discourages road authorities from improving the level of safety with proactive motivation. This study suggests how to apply a principle of competition for roads, in particular by means of performance evaluation. It first discusses why road infrastructure has been slow in safety oriented development and management in respect of its business model. Then it suggests some practical ways of how to promote road safety between road authorities, particularly by evaluating safety performance of road infrastructure. These are summarized as decision of safety performance indicators, classification of spatial boundaries, data collection, evaluation, and reporting. Some consideration points are also discussed to make safety performance evaluation on road infrastructure lead to better road safety management. PMID:25374273

  8. Efficacy, safety, quality control, marketing and regulatory guidelines for herbal medicines (phytotherapeutic agents)

    OpenAIRE

    Calixto, J B

    2000-01-01

    This review highlights the current advances in knowledge about the safety, efficacy, quality control, marketing and regulatory aspects of botanical medicines. Phytotherapeutic agents are standardized herbal preparations consisting of complex mixtures of one or more plants which contain as active ingredients plant parts or plant material in the crude or processed state. A marked growth in the worldwide phytotherapeutic market has occurred over the last 15 years. For the European and USA market...

  9. Mammalian safety of microbial agents for vector control: a WHO Memorandum*

    OpenAIRE

    1981-01-01

    This Memorandum outlines recommended safety tests for application to biological agents under consideration for widespread use for pest control. The basic principles utilized in developing these recommendations were that: (i) the hazards presented by microbial pesticides are inherently different from those associated with chemical pesticides and the tests used to determine hazard potential to man should reflect this; (ii) a high proportion of negative results is likely; (iii) tiered testing sy...

  10. Tools for seismic safety evaluation of structures

    International Nuclear Information System (INIS)

    The Hanshin-Awaji earthquake (January 17, 1995) clearly demonstrated that the occurrence of very strong ground motion in the area near the seismic fault is capable of causing severe structural damage beyond general estimation. It has emphasized the importance of earthquake engineering research into why and how structures collapse in real earthquake conditions and these processes are reproduced numerically. For this purpose, we need to develop the research tools, which will understand the characteristics of input earthquake motion and structural dynamic behaviors during earthquake. These tools are useful not only the seismic evaluation of the design structures but also the reevaluation of existing structures. After the Hanshin-Awaji earthquake, the National Research Institute for Earth Science and Disaster Prevention (NIED) and Science and Technology Agency (STA) decided as two action plans for the construction of the above-mentioned tools. The one is construct the strong motion observation network. The other one is the construction plan of the world largest shaking table facility, which is aimed to understand the failure process in real earthquake condition. In this paper, we report the main feature of K-NET and 3-D full-scale earthquake testing facility, the usage of these tools in the future for the seismic safety evaluation of structures, and the worldwide collaboration research capability. (author)

  11. Needs for development of criticality safety evaluation system

    International Nuclear Information System (INIS)

    This paper provides an outline of development of a new criticality safety evaluation code system. The new system includes not only continuous energy Monte Carlo codes MVP and MCNP but also JACS code system traditionally used for criticality safety assessment of nuclear fuel cycle facility in Japan. The purpose of the new code system development is criticality safety evaluation of spent nuclear fuels taking burnup credit into account and error evaluation of criticality calculations. (author)

  12. Using dataflow traceability between functions in the safety evaluation process

    OpenAIRE

    Lemaire, E.; LESNE, F; BAYART, M

    2006-01-01

    This paper deals with the safety evaluation process required by law for high safety related system in rail in Europe. A methodology is given to guide the independent analysis and evaluation process. In a general framework for requirement engineering process, the proposed methodology aims at speeding up the process of safety evaluation and to facilitate the work of the independent checker and of the assessor of the system in a systematic way. The methodology is based on a functional analysis a...

  13. Quantitative Evaluation of Contrast Agent Dynamics in Liver MRI

    OpenAIRE

    Dahlström, Nils

    2010-01-01

    The studies presented here evaluate the biliary, parenchymal and vascular enhancement effects of two T1-shortening liver-specific contrast agents, Gd-BOPTA and Gd-EOB-DTPA, in Magnetic Resonance Imaging (MRI) of healthy subjects and of patients. Ten healthy volunteers were examined with both contrast agents in a 1.5 T MRI system using three-dimensional gradient echo sequences for dynamic imaging until five hours after injection. The enhancement of the common hepatic duct in contrast to the li...

  14. Biological safety evaluation of the modified urinary catheter

    Energy Technology Data Exchange (ETDEWEB)

    Kowalczuk, Dorota, E-mail: dorota.kowalczuk@umlub.pl [Department of Medicinal Chemistry, Medical University of Lublin, Jaczewskiego 4, 20-090 Lublin (Poland); Przekora, Agata; Ginalska, Grazyna [Department of Biochemistry and Biotechnology, Medical University of Lublin, Chodzki 1, 20-093 Lublin (Poland)

    2015-04-01

    The purpose of this study was to evaluate in vitro safety of the novel tosufloxacin (TOS)-treated catheters with the prolonged antimicrobial activity. The test samples of silicone latex catheter were prepared by the immobilization of TOS on chitosan (CHIT)-coated catheter by means of covalent bonds and non-covalent interactions. Each step of the modification process of catheter surface was observed using ATR–Fourier transform infrared spectroscopy. In vitro cytotoxicity of the modified and unmodified catheters was assessed by direct and indirect tests in accordance with ISO standards using green monkey kidney (GMK) cell line. The MTT, lactate dehydrogenase activity (LDH), WST-8, Sulforhodamine B (SRB) test results and microscopic observation clearly indicated that unmodified silicone latex catheters decrease cell metabolic activity, act as a cytotoxic agent causing cell lysis and induce cell death through necrotic or apoptotic process. We suggest that chitosan coat with TOS immobilized limits leaching of harmful agents from silicone latex material, which significantly enhances survivability of GMK cells and therefore is quite a good protection against the cytotoxic effect of this material. - Highlights: • Characterization of the novel antimicrobial urinary catheters • Monitoring of the catheter modification by FTIR analysis • Confirmation of high cytotoxicity of latex-based catheter used in urological practice • Chitosan-coated and tosufloxacin-treated catheter is less toxic than the untreated one. • The proposed surface modification protects cells against latex-induced death.

  15. Biological safety evaluation of the modified urinary catheter

    International Nuclear Information System (INIS)

    The purpose of this study was to evaluate in vitro safety of the novel tosufloxacin (TOS)-treated catheters with the prolonged antimicrobial activity. The test samples of silicone latex catheter were prepared by the immobilization of TOS on chitosan (CHIT)-coated catheter by means of covalent bonds and non-covalent interactions. Each step of the modification process of catheter surface was observed using ATR–Fourier transform infrared spectroscopy. In vitro cytotoxicity of the modified and unmodified catheters was assessed by direct and indirect tests in accordance with ISO standards using green monkey kidney (GMK) cell line. The MTT, lactate dehydrogenase activity (LDH), WST-8, Sulforhodamine B (SRB) test results and microscopic observation clearly indicated that unmodified silicone latex catheters decrease cell metabolic activity, act as a cytotoxic agent causing cell lysis and induce cell death through necrotic or apoptotic process. We suggest that chitosan coat with TOS immobilized limits leaching of harmful agents from silicone latex material, which significantly enhances survivability of GMK cells and therefore is quite a good protection against the cytotoxic effect of this material. - Highlights: • Characterization of the novel antimicrobial urinary catheters • Monitoring of the catheter modification by FTIR analysis • Confirmation of high cytotoxicity of latex-based catheter used in urological practice • Chitosan-coated and tosufloxacin-treated catheter is less toxic than the untreated one. • The proposed surface modification protects cells against latex-induced death

  16. Evaluation of the Efficacy of Targeted Imaging Agents.

    Science.gov (United States)

    Graham, Michael M; Weber, Wolfgang A

    2016-04-01

    This paper presents our adaptation of Fryback and Thornbury's hierarchical scheme for modeling the efficacy of diagnostic imaging systems. The original scheme was designed to evaluate new medical imaging systems but is less successful when applied to evaluate new radiopharmaceuticals. The proposed adaptation, which is specifically directed toward evaluating targeted imaging agents, has 6 levels: in vitro characterization, in vivo animal studies, initial human studies, impact on clinical care (change in management), impact on patient outcome, and societal efficacy. These levels, particularly the first four, implicitly define the sequence of studies needed to move an agent from the radiochemistry synthesis laboratory to the clinic. Completion of level 4 (impact on clinical care) should be sufficient for initial approval and reimbursement. We hope that the adapted scheme will help streamline the process and assist in bringing new targeted radiopharmaceuticals to approval over the next few years. PMID:26769867

  17. Criticality Safety Evaluation of a LLNL Training Assembly for Criticality Safety (TACS)

    International Nuclear Information System (INIS)

    Hands-on experimental training in the physical behavior of multiplying systems is one of ten key areas of training required for practitioners to become qualified in the discipline of criticality safety as identified in DOE-STD-1135-99, ''Guidance for Nuclear Criticality Safety Engineer Training and Qualification''. This document is a criticality safety evaluation of the training activities (or operations) associated with HS-3200, ''Laboratory Class for Criticality Safety''. These activities utilize the Training Assembly for Criticality Safety (TACS). The original intent of HS-3200 was to provide LLNL fissile material handlers with a practical hands-on experience as a supplement to the academic training they receive biennially in HS-3100, ''Fundamentals of Criticality Safety'', as required by ANSI/ANS-8.20-1991, ''Nuclear Criticality Safety Training''. HS-3200 is to be enhanced to also address the training needs of nuclear criticality safety professionals under the auspices of the NNSA Nuclear Criticality Safety Program

  18. Evaluation of Safety Culture Implementation and Socialization Results

    International Nuclear Information System (INIS)

    Evaluation of safety culture implementation and socialization results has been perform. Evaluation is carried out with specifying safety culture indicators, namely: Meeting between management and employee, system for incidents analysis, training activities related to improving safety, meeting with regulator, contractors, surveys on behavioural attitudes, and resources allocated to promote safety culture. Evaluation is based on observation and visiting the facilities to show the compliance indicator in term of good practices in the frame of safety culture implementation. For three facilities of research reactors, Kartini Yogyakarta, TRIGA Mark II Bandung and MPR-GAS Serpong, implementation of safety culture is considered good enough and progressive. Furthermore some indicator should be considered more intensive, for example the allocated resources, self assesment based on own questionnaire in the frame of improving the safety culture implementation. (author)

  19. Food Safety Evaluation System Construction Based on Artificial Neural Network

    OpenAIRE

    Jian Wang; Zhenmin Tang; Xianli Jin

    2015-01-01

    This study uses regression model and artificial neural network model to apply food safety index in food safety trend predication and makes policy advices in the construction and release of an authoritative food safety index, The results showed that the BP neural network was high-precision, fast and objective, which could be used to food safety evaluation of circulation links of production, processing and sales.

  20. Food Safety Evaluation System Construction Based on Artificial Neural Network

    Directory of Open Access Journals (Sweden)

    Jian Wang

    2015-05-01

    Full Text Available This study uses regression model and artificial neural network model to apply food safety index in food safety trend predication and makes policy advices in the construction and release of an authoritative food safety index, The results showed that the BP neural network was high-precision, fast and objective, which could be used to food safety evaluation of circulation links of production, processing and sales.

  1. Development and Evaluation of Food Safety Signs

    OpenAIRE

    O'Connor, Sandra

    2009-01-01

    Food borne disease continues to be a significant public health concern. The increasing awareness of food borne illness intensifies the need for proper food safety education among food handlers. The objectives of this study were to develop bilingual (English/Spanish) food safety signs, to determine their comprehensibility and most effective delivery mechanism for presentation to food handlers. The food safety concepts developed into images were: cross-contamination, proper use of thermometer t...

  2. Evaluation of operating experience with safety values

    International Nuclear Information System (INIS)

    This report describes statistical investigations of 2076 functional tests carried out on power operated safety valves in conventional power plants in 1972 until 1983 with special regard to Common Mode-Failures. The results clearly show that Common Mode-Failures play an important part of non-availability for the controlled safety valves, especially in the control system. The 'Deutsche Risikostudie' does not consider any Common Mode-Failures of the primary safety valves. However there is no significant increase of the risk resulted by the primary safety valves in the 'Referenzanlage' if the calculated Common Mode-Failures probabilities are considered. (orig.)

  3. Radionuclide sorption from the safety evaluation perspective

    International Nuclear Information System (INIS)

    Research and development directed towards the assessment of the long-term performance of radioactive waste disposal systems has been recognised as a priority area with a strong need for international co-operation and co-ordination. The ultimate aims is to promote the quality and credibility of safety assessment techniques for radioactive waste disposal. Sorption in the geosphere is one of the key processes for retarding the transport of radionuclide from the underground disposal facility to the biosphere. In many cases, sorption in the near field and in the biosphere is also important. A workshop, organised to favor discussion around a small number of invited papers, was held in October 1991: - to evaluate critically the way sorption processes are incorporated in performance assessment models; - to identify open issues of high priority, and; - to propose future activities to resolve these issues. These proceedings reproduce the invited papers and the conclusions and recommendations adopted by the workshop. Eight papers are in the INIS SCOPE. The main subjects studied are: sorption database comparison, sorption database development and three case studies, experimental techniques, adsorption models

  4. Development of inspection safety evaluation technology

    International Nuclear Information System (INIS)

    The purpose of this project is to protection nation inspector's over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector's over exposure from radiation at domestic nuclear facilities. Management of inspector's exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint research for development of the special radiation measurement and analysis has been prepared. (author). 21 tabs., 24 figs., 20 refs

  5. Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation

    International Nuclear Information System (INIS)

    One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

  6. Implementation and Evaluation of an Virtual Intelligent Agent

    OpenAIRE

    Moore, Mary; Ahmed, Terry

    2003-01-01

    Reference librarians at the National Library of Medicine answer over 100,000 client questions annually. Although many answers are the NLM Web, clients may have difficulty finding them. Using intelligent virtual agent software, the NLM launched Cosmo, the Customer Service Owl (http://wwwns.nlm.nih.gov/). Cosmo uses natural language pattern matching to answer common questions. Early evaluation shows Cosmo can answer 25% of questions asked, but some users mistake the service for chat reference o...

  7. Guide for understanding and evaluation of safety culture

    International Nuclear Information System (INIS)

    This report was the guide of understanding and evaluation of safety culture. Operator's activities for enhancement of safety culture in nuclear installations became an object of safety regulation in the management system. Evaluation of operator's activities (including top management's involvement) to prevent degradation of safety culture and organization climate in daily works needed understanding of safety culture and diversity of operator's activities. This guide was prepared to check indications of degradation of safety culture and organization climate in operator's activities in daily works and encourage operator's activities to enhance safety culture improvement and good practice. Comprehensive evaluation of operator's activities to prevent degradation of safety culture and organization climate would be performed from the standpoints of 14 safety culture elements such as top management commitment, clear plan and implementation of upper manager, measures to avoid wrong decision making, questioning attitude, reporting culture, good communications, accountability and openness, compliance, learning system, activities to prevent accidents or incidents beforehand, self-assessment or third party evaluation, work management, change management and attitudes/motivation. Element-wise examples and targets for evaluation were attached with evaluation check tables. (T. Tanaka)

  8. Long-term follow-up of MCL patients treated with single-agent ibrutinib: updated safety and efficacy results

    OpenAIRE

    Wang, Michael L.; Blum, Kristie A.; Martin, Peter; Goy, Andre; Auer, Rebecca; Kahl, Brad S.; Jurczak, Wojciech; Advani, Ranjana H.; Romaguera, Jorge E.; Williams, Michael E.; Barrientos, Jacqueline C.; Chmielowska, Ewa; Radford, John; Stilgenbauer, Stephan; Dreyling, Martin

    2015-01-01

    Ibrutinib demonstrates durable responses and sustained single-agent activity in relapsed or refractory MCL at median 26.7-month follow-up.Ibrutinib shows a favorable benefit-risk profile over time, with a manageable safety profile.

  9. Safety analysis and evaluation methodology for fusion systems

    International Nuclear Information System (INIS)

    Three issues are critical to the public acceptability of nuclear fusion as an energy system. These are technological feasibility, economic viability and safety. Safety will be especially important when tritium is used as a fuel and the reactor becomes radioactive. As a result of this study a safety analysis and evaluation methodology for fusion systems were developed. In this all the safety-related issues in the fusion system could be integrated and resolved. A general descriptive model, the three principle items to be assured, an approach to safety assurance based on event categorization and the function based safety analysis are all discussed. The usefulness of the methodology was illustrated by the application of the safety evaluation to the R-Tokamak. (author)

  10. 2005 dossier: clay. Tome: safety evaluation of the geologic disposal

    International Nuclear Information System (INIS)

    This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of an argilite-type geologic disposal facility for high-level and long-lived (HLLL) radioactive wastes. Content: 1 - safety approach: context and general goals, general safety principles, specificity of the argilite repository safety approach, general approach; 2 - general description: HLLL wastes, geologic context of the Meuse/Haute-Marne site, repository architecture; 3 - safety functions and disposal design: time and space scales, safety approach by functions, functional analysis methodology, analysis of safety functions during the construction, exploitation and observation phases, safety functions analysis during post-closure phase; 4 - operational safety: dosimetric evaluation, risk analysis (explosible gases, fire hazards, lift cage drop, container drop); 5 - long-term efficiency of the disposal facility: normal evolution scenario, from conceptual models to the safety calculation model, description of the safety model, quantitative evaluation of the normal evolution scenario, main lessons learnt from the efficiency analysis; 6 - management of uncertainties: identification, building up of altered situations, mastery of uncertainties; 7 - evaluation of altered evolution scenarios: sealing defect scenario, container defect scenario, drilling scenario, strongly degraded operation scenario; 8 - conclusions: lessons learnt, possible improvements. (J.S.)

  11. The safety-critical software evaluation assistant (SEA)

    Energy Technology Data Exchange (ETDEWEB)

    Persons, W.L.

    1995-10-01

    The Computer Safety and Reliability Group at Lawrence Livermore National Laboratory (LLNL) is researching the evaluation of software used in safety-critical applications. This paper describes one, of the research and development efforts currently underway to model the software evaluation process and to develop a software evaluation tool. One of the primary techniques available for determining the safety of software proposed for use in safety-critical applications is to evaluate the software development process and the resulting products. This model of the evaluation process was influenced by several factors the underlying motivation was to identify, control and reduce the risk inherent in building safety-critical software systems. This prototype tool, the Software Evaluation Assistant (SEA), assists and guides evaluators as they analyze safety-critical software. SEA describes specific evaluation goals, provides a brief overview of the specific evaluation process, identifies potential, risks of not performing the evaluation, identifies the skills required to carry out the evaluation of a particular topic, identifies the material that should typically be available for the evaluation, and poses questions used to examine and rate the software item.

  12. Safety evaluation of asphalt products, (1)

    International Nuclear Information System (INIS)

    The safety of activity-containing asphalt products kept in enclosed storage was evaluated from considerations of radiolysis and hydrogen evolution. The samples examined were mainly homogeneous asphalt products containing 43w/0 of sludge produced in routine operation of the asphalt plant at the Japan Atomic Energy Research Institute (JAERI), the samples were irradiated with external 60Co γ-ray source to a dose of 109 R. The bulk of the gases evolving from the asphalt product is hydrogen, which constitutes 75 -- 95% of the total gas evolution. The total amount of gases generated during infinite time is proportional to the total exposure dose; hydrogen evolves at a rate of 5.5x10-3 cm3/g.MR. The amount of total gas evolution is governed solely by the quantity of asphalt, and is independent of the sludge contained therein. Nor do differences in the rate of dose appear to have any significant effect. In so far as concerns smallness of radiolysis, slightly better performance can be expected from straight than from blown asphalt. There is no danger of explosion of the asphalt products currently generated at JAERI (10-5 Ci/kg), which can be expected to accumulate in infinite time no more than about 3 cm3 from a 200 l product. Only asphalt products containing activity in concentrations exceeding 10-1 Ci/kg risk explosion when kept in enclosed storage, through accumulation of hydrogen in quantity exceeding the explosion limit in a relatively short time. (auth.)

  13. Development of the design safety evaluation technology

    International Nuclear Information System (INIS)

    The objective of this research is to develop a deterministic and probabilistic safety assessment technology for reactor safety. As KOSAC/MOD1 which has been developed for the deterministic safety assessment and uses one dimensional, 3-equation, homogeneous thermal-hydraulic model with drift flux correlation, is an early version, so there are some limitations for its application and it has not been verified sufficiently. For its improvement and futher verification, CATHARE computer code and BETHSY experiments are also analyzed. The research areas of the probabilistic safety assessment(PSA) are development of a computer code package to perform a consistent PSA and computerized systems which aid the analysis in performance of PSA e.g., in the analysis of common-cause failure and HREP in the analysis of human reliability. A new technology such as artificial intelligence(AI) is also utilized in order to improve present PSA technique. (Author)

  14. Developing a comprehensive safety performance evaluation framework for Saudi schools

    OpenAIRE

    Turki Alolah; Rodney Anthony Stewart; Kriengsak Panuwatwanich; Sherif Mohamed

    2014-01-01

    Purpose – The purpose of this paper is to empirically develop a safety performance (SP) framework for evaluating the various leading and lagging indicators of SP in Saudi public schools. Design/methodology/approach – A comprehensive review of the safety and performance evaluation literature enabled the formulation of the constructs, factors and items that underpinned a conceptual SP evaluation framework. The research method involved a conceptual framework review and refinement process with 18...

  15. Criticality safety benchmark evaluation project: Recovering the past

    Energy Technology Data Exchange (ETDEWEB)

    Trumble, E.F.

    1997-06-01

    A very brief summary of the Criticality Safety Benchmark Evaluation Project of the Westinghouse Savannah River Company is provided in this paper. The purpose of the project is to provide a source of evaluated criticality safety experiments in an easily usable format. Another project goal is to search for any experiments that may have been lost or contain discrepancies, and to determine if they can be used. Results of evaluated experiments are being published as US DOE handbooks.

  16. Research on the Evaluation System for Rural Public Safety Planning

    OpenAIRE

    Sun, Ming; YAN, Jianxin

    2014-01-01

    The indicator evaluation system is introduced to the study of rural public safety planning in this article. By researching the current rural public safety planning and environmental carrying capacity, we select some carrying capacity indicators influencing the rural public safety, such as land, population, ecological environment, water resources, infrastructure, economy and society, to establish the environmental carrying capacity indicator system. We standardize the indicators, use gray corr...

  17. Criticality Safety Evaluation of Hanford Tank Farms Facility

    Energy Technology Data Exchange (ETDEWEB)

    WEISS, E.V.

    2000-12-15

    Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

  18. Criticality Safety Evaluation of Hanford Tank Farms Facility

    International Nuclear Information System (INIS)

    Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste

  19. Research on the Evaluation System for Rural Public Safety Planning

    Institute of Scientific and Technical Information of China (English)

    Ming; SUN; Jianxin; YAN

    2014-01-01

    The indicator evaluation system is introduced to the study of rural public safety planning in this article.By researching the current rural public safety planning and environmental carrying capacity,we select some carrying capacity indicators influencing the rural public safety,such as land,population,ecological environment,water resources,infrastructure,economy and society,to establish the environmental carrying capacity indicator system.We standardize the indicators,use gray correlation analysis method to determine the weight of indicators,and make DEA evaluation of the indicator system,to obtain the evaluation results as the basis for decision making in rural safety planning,and provide scientific and quantified technical support for rural public safety planning.

  20. TA-55 Final Safety Analysis Report Comparison Document and DOE Safety Evaluation Report Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Alan Bond

    2001-04-01

    This document provides an overview of changes to the currently approved TA-55 Final Safety Analysis Report (FSAR) that are included in the upgraded FSAR. The DOE Safety Evaluation Report (SER) requirements that are incorporated into the upgraded FSAR are briefly discussed to provide the starting point in the FSAR with respect to the SER requirements.

  1. Synthesis and Evaluation of Some Coumarin Containing Potential Antimicrobial Agents

    OpenAIRE

    Kudale, Sayali D.; Meenakshi N. Deodhar

    2012-01-01

    A series of the Schiff’s bases incorporating coumarin and chalcone moeities, 3-(4-(4-(substituted phenyl)prop-1-ene-3-one) phenylimino) methyl)-4-chloro-2h-chromen-2-one 4(a-g) were synthesized as potential antimicrobial agents. These compounds were characterized on the basis of their spectral (IR, 1H NMR) data and evaluated for antimicrobial activity in vitro against gram positive and gram negative bacteria and fungi. Compound 4b was found to be most active with an MIC of 20 µg/mL against al...

  2. Analytic choices in road safety evaluation

    DEFF Research Database (Denmark)

    Elvik, Rune

    2012-01-01

    Conducting rigorous before-and-after studies is essential for improving knowledge regarding the effects of road safety measures. However, state-of-the-art approaches like the empirical Bayes or fully Bayesian techniques cannot always be applied, as the data required by these approaches may be...

  3. Efficacy and safety of lanthanoids as X-ray contrast agents

    International Nuclear Information System (INIS)

    suited for higher X-ray tube voltages, particularly CT examinations. However, Ln-specific induction of NSF-like skin lesions and rapid elevation of pro-fibrotic serum cytokines levels were observed in rats following multiple administrations of high doses of Ln-DTPA-BMA complexes. The results of this animal study suggest that the stability of lanthanoid complexes may be an important consideration in evaluating the potential for in vivo safety. Furthermore the results suggest a potential of the entire class of lanthanoids to have the potential to trigger NSF-like skin lesions in rats rather than only some of the specific elements of this series.

  4. Efficacy and safety of lanthanoids as X-ray contrast agents

    Energy Technology Data Exchange (ETDEWEB)

    Pietsch, Hubertus, E-mail: Hubertus.Pietsch@bayerhealthcare.com [Contrast Media Research, Bayer Schering Pharma AG, 13353 Berlin (Germany); Jost, Gregor, E-mail: Gregor.Jost@bayerhealthcare.com [Contrast Media Research, Bayer Schering Pharma AG, 13353 Berlin (Germany); Frenzel, Thomas, E-mail: Thomas.Frenzel@bayerhealthcare.com [Contrast Media Research, Bayer Schering Pharma AG, 13353 Berlin (Germany); Raschke, Marian, E-mail: Marian.Raschke@bayerhealthcare.com [Nonclinical Drug Safety, Bayer Schering Pharma AG, Berlin (Germany); Walter, Jakob, E-mail: Jakob.Walter@bayerhealthcare.com [Nonclinical Drug Safety, Bayer Schering Pharma AG, Berlin (Germany); Schirmer, Heiko, E-mail: Heiko.Schirmer@bayerhealthcare.com [Medical Chemistry VI, Bayer Schering Pharma AG, Berlin (Germany); Huetter, Joachim, E-mail: Joachim.Hutter@bayerhealthcare.com [Contrast Media Research, Bayer Schering Pharma AG, 13353 Berlin (Germany); Sieber, Martin A., E-mail: martin.sieber@bayerhealthcare.com [Contrast Media Research, Bayer Schering Pharma AG, 13353 Berlin (Germany)

    2011-11-15

    suited for higher X-ray tube voltages, particularly CT examinations. However, Ln-specific induction of NSF-like skin lesions and rapid elevation of pro-fibrotic serum cytokines levels were observed in rats following multiple administrations of high doses of Ln-DTPA-BMA complexes. The results of this animal study suggest that the stability of lanthanoid complexes may be an important consideration in evaluating the potential for in vivo safety. Furthermore the results suggest a potential of the entire class of lanthanoids to have the potential to trigger NSF-like skin lesions in rats rather than only some of the specific elements of this series.

  5. Efficacy, safety, quality control, marketing and regulatory guidelines for herbal medicines (phytotherapeutic agents

    Directory of Open Access Journals (Sweden)

    J.B. Calixto

    2000-02-01

    Full Text Available This review highlights the current advances in knowledge about the safety, efficacy, quality control, marketing and regulatory aspects of botanical medicines. Phytotherapeutic agents are standardized herbal preparations consisting of complex mixtures of one or more plants which contain as active ingredients plant parts or plant material in the crude or processed state. A marked growth in the worldwide phytotherapeutic market has occurred over the last 15 years. For the European and USA markets alone, this will reach about $7 billion and $5 billion per annum, respectively, in 1999, and has thus attracted the interest of most large pharmaceutical companies. Insufficient data exist for most plants to guarantee their quality, efficacy and safety. The idea that herbal drugs are safe and free from side effects is false. Plants contain hundreds of constituents and some of them are very toxic, such as the most cytotoxic anti-cancer plant-derived drugs, digitalis and the pyrrolizidine alkaloids, etc. However, the adverse effects of phytotherapeutic agents are less frequent compared with synthetic drugs, but well-controlled clinical trials have now confirmed that such effects really exist. Several regulatory models for herbal medicines are currently available including prescription drugs, over-the-counter substances, traditional medicines and dietary supplements. Harmonization and improvement in the processes of regulation is needed, and the general tendency is to perpetuate the German Commission E experience, which combines scientific studies and traditional knowledge (monographs. Finally, the trend in the domestication, production and biotechnological studies and genetic improvement of medicinal plants, instead of the use of plants harvested in the wild, will offer great advantages, since it will be possible to obtain uniform and high quality raw materials which are fundamental to the efficacy and safety of herbal drugs.

  6. K Basins consolidated fuel storage and handling criticality safety evaluation

    International Nuclear Information System (INIS)

    The bases for safe storage of irradiated N Reactor and Single Pass Reactor (SPR) fuel in the Hanford K Basins, as derived from Existing Criticality Safety Evaluation reports, have been consolidated in one supporting document

  7. Hyperspectral and multispectral imaging for evaluating food safety and quality

    Science.gov (United States)

    Spectral imaging technologies have been developed rapidly during the past decade. This paper presents hyperspectral and multispectral imaging technologies in the area of food safety and quality evaluation, with an introduction, demonstration, and summarization of the spectral imaging techniques avai...

  8. An evaluation of the uranium mine radiation safety course

    International Nuclear Information System (INIS)

    The report evaluates the Uranium Mine Radiation Safety Course focussing on the following areas: effectivenss of the course; course content; instructional quality; course administration. It notes strengths and weaknesses in these areas and offers preliminary recommendations for future action

  9. Evaluation on safety concerns of integral reactor: development of safety analysis technology for integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, W. S.; Kim, W. K.; Yun, Y. G.; Ahn, H. J.; Lee, J. S.; Lee, S. G.; Sin, A. D. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-03-01

    The Nuclear Desalination Plant (NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in a present study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current light water reactor and advanced reactor designs, and user requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified and discussed. They includes the use of proven technology for new safety features, systematic event classification and selection, strengthening containment function, and the safety impacts on desalination-related systems. These efforts to identify and technically resolve the safety concerns in the design stage will provide the early confidence of SMART safety and the technical basis to evaluate the safety to designers and reviewers in the future. 62 refs., 3 figs., 21 tabs. (Author)

  10. Sequential Generalized Likelihood Ratio Tests for Vaccine Safety Evaluation

    OpenAIRE

    Shih, Mei-Chiung; Lai, Tze Leung; Heyse, Joseph F; Chen, Jie

    2010-01-01

    The evaluation of vaccine safety involves pre-clinical animal studies, pre-licensure randomized clinical trials and post-licensure safety studies. Sequential design and analysis are of particular interest because they allow early termination of the trial or quick detection that the vaccine exceeds a prescribed bound on the adverse event rate. After a review of recent developments in this area, we propose a new class of sequential generalized likelihood ratio tests for evaluating adverse event...

  11. Evaluation of surgical nurses’ attitudes concerning patient safety

    OpenAIRE

    Ali Şahin; Fatma Ayhan; Şerife Kurşun

    2015-01-01

    The present study was designed as a descriptive study to evaluate the attitudes of surgical nurses concerning patient safety. The study included 123 nurses, who have been working in the operating rooms of the hospitals in Karaman, Konya for at least one year and were voluntary to participate in the study. Data collection tools included a questionnaire to inquire demographic characteristics of surgical nurses, and “Safety Attitudes Questionnaire (SAQ) -Operating Room Version” to evaluate their...

  12. Safety analysis and evaluation methodology for fusion systems

    International Nuclear Information System (INIS)

    A synthesized methodology of safety analysis and evaluation for general fusion systems is proposed. In the course of the methodology development, its main frame has been constructed in order to take account of all safety-related items and to ensure a logical consistency. The safety-related items are divided broadly into two groups. One of them is the public protection from radiological hazard, which is introduced as a safety requirement from an external viewpoint for the fusion system. The other items are the matter from an internal viewpoint and are related to the fusion system behavior in itself. These items are composed of the understanding of a fusion system, the safety ensuring principle and the function based safety analysis. All of these items have been mapped on the frame, considering the mutual relations, among them, consistently. To complete the methodology development, the safety evaluation for the actual design of a fusion system has been performed in conformity to this methodology. Thus, it has been demonstrated that the methodology proposed here is appropriate to the safety analysis and evaluation for the fusion system. (author). 9 refs, 4 figs, 2 tabs

  13. Systematic evaluation of safety in old nuclear power plants

    International Nuclear Information System (INIS)

    A systematic evaluation program of the early nuclear power plant has been conducted by the French safety authorities. This examination is concerned with the remodelling of safety documents (safety reports, operation general regulations, incident and accident procedures, internal emergency plans and organization manuals for quality), with an analysis of the operating experience in frequently utilized circuits and with a systematic analysis of safeguards circuits. These evaluations are based on the experience of the Ardennes nuclear power plant, operating 15 years. This paper also describes the main studies and modifications undertaken in this power plant

  14. Evaluating safety-critical organizations - emphasis on the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, Teemu; Oedewald, Pia (VTT, Technical Research Centre of Finland (Finland))

    2009-04-15

    An organizational evaluation plays a key role in the monitoring, as well as controlling and steering, of the organizational safety culture. If left unattended, organizations have a tendency to gradually drift into a condition where they have trouble identifying their vulnerabilities and mechanisms or practices that create or maintain these vulnerabilities. The aim of an organizational evaluation should be to promote increased understanding of the sociotechnical system and its changing vulnerabilities. Evaluation contributes to organizational development and management. Evaluations are used in various situations, but when the aim is to learn about possible new vulnerabilities, identify organizational reasons for problems, or prepare for future challenges, the organization is most open to genuine surprises and new findings. It is recommended that organizational evaluations should be conducted when - there are changes in the organizational structures - new tools are implemented - when the people report increased workplace stress or a decreased working climate - when incidents and near-misses increase - when work starts to become routine - when weak signals (such as employees voicing safety concerns or other worries, the organization 'feels' different, organizational climate has changed) are perceived. In organizations that already have a high safety level, safety managers work for their successors. This means that they seldom see the results of their successful efforts to improve safety. This is due to the fact that it takes time for the improvement to become noticeable in terms of increased measurable safety levels. The most challenging issue in an organizational evaluation is the definition of criteria for safety. We have adopted a system safety perspective and we state that an organization has a high potential for safety when - safety is genuinely valued and the members of the organization are motivated to put effort on achieving high levels of safety

  15. Evaluating safety-critical organizations - emphasis on the nuclear industry

    International Nuclear Information System (INIS)

    An organizational evaluation plays a key role in the monitoring, as well as controlling and steering, of the organizational safety culture. If left unattended, organizations have a tendency to gradually drift into a condition where they have trouble identifying their vulnerabilities and mechanisms or practices that create or maintain these vulnerabilities. The aim of an organizational evaluation should be to promote increased understanding of the sociotechnical system and its changing vulnerabilities. Evaluation contributes to organizational development and management. Evaluations are used in various situations, but when the aim is to learn about possible new vulnerabilities, identify organizational reasons for problems, or prepare for future challenges, the organization is most open to genuine surprises and new findings. It is recommended that organizational evaluations should be conducted when - there are changes in the organizational structures - new tools are implemented - when the people report increased workplace stress or a decreased working climate - when incidents and near-misses increase - when work starts to become routine - when weak signals (such as employees voicing safety concerns or other worries, the organization 'feels' different, organizational climate has changed) are perceived. In organizations that already have a high safety level, safety managers work for their successors. This means that they seldom see the results of their successful efforts to improve safety. This is due to the fact that it takes time for the improvement to become noticeable in terms of increased measurable safety levels. The most challenging issue in an organizational evaluation is the definition of criteria for safety. We have adopted a system safety perspective and we state that an organization has a high potential for safety when - safety is genuinely valued and the members of the organization are motivated to put effort on achieving high levels of safety - it is

  16. Safety evaluation of the KNICS digital reactor protection system

    International Nuclear Information System (INIS)

    Korean Nuclear I and C System (KNICS) project, a national research program for developing a safety-class digital system, has designed a new reactor protection system (RPS). The usage of digital equipment in a safety critical application increases the importance of a risk evaluation since microprocessors and software technologies make the digital system very complex and their unavailability is hard to quantify. This paper addresses the safety evaluation of the KNICS RPS in consideration of the several technical concerns of a safety modeling for a digital system. We also present the fault-tree modeling technique and the risk evaluation results. A fault-tree model which includes the common cause failure events, the coverage of a fault-tolerant mechanism and the software failure event is developed. Based on the minimal cut sets of the model, we discuss the system unavailability of the newly developed design of the KNICS RPS

  17. [Safety evaluation of Chinese medicine on tumor therapy].

    Science.gov (United States)

    Liu, Rui; Hua, Bao-Jin; Li, Jie

    2013-12-01

    As a characteristic tumor therapy in China, Chinese medicine (CM) plays an important position in comprehensive treatment of tumor. It's a critical issue of objective realization, analysis and evaluation of CM safety for scientific decision-making in tumor safe medication and it also is a pivotal issue which affects the international communication. The safety evaluation of CM includes three phases: pre-clinical safety evaluation, clinical trials (micro-dose studies and traditional clinical trials) and post-marketing CM safety assessment. The key point of evaluation should be distinguished among different stages and various types of CM (such as classic formulas, Chinese herbal extracts, etc). Emphasis should be given to chronic toxicity when evaluating oral Chinese herbal , microdose studies and quality control must be underlined while injection is evaluated and more attention should be pay to the dose-effect relationship and time-effect relationship when turned to toxic Chinese medicine , and so as for the toxicity grading study. Moreover, we should constantly improve CM safety assessment method in various stages of tumor treatment, such as introducing the concept of syndrome classification theory, bringing in metabonomics and real-world research method which are similar to the CM therapeutic concept. Most importantly, we must keep its own feature of CM theory when we learn the concept of safety evaluation from abroad. Actively exploring the anti-tumor medicine safety evaluation methods and strategies is of great significance for clinical and experimental research, and it can provide supportability platform to CM's international communication. PMID:24791513

  18. Development of safety analysis technology for integral reactor; evaluation on safety concerns of integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hee Chul; Kim, Woong Sik; Lee, J. H. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2002-03-01

    The Nuclear Desalination Plant (NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in this study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current light water reactor and advanced reactor designs, and user requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified and discussed. They include the use of proven technology for new safety features, systematic event classification and selection, strengthening containment function, and the safety impacts on desalination-related systems. The study presents the general safety requirements applicable to licensing of an integral reactor and suggests additional regulatory requirements, which need to be developed, based on the direction to resolution of the safety concerns. The efforts to identify and technically resolve the safety concerns in the design stage will provide the early confidence of SMART safety and the technical basis to evaluate the safety to designers and reviewers in the future. Suggestion on the development of additional regulatory requirements will contribute for the regulator to taking actions for licensing of an integral reactor. 66 refs., 5 figs., 24 tabs. (Author)

  19. Evaluation of radiolabeled ruthenium compounds as tumor-localizing agents

    International Nuclear Information System (INIS)

    This work introduces a new class of radiopharmaceuticals based on ruthenium-97. The excellent physical properties of Ru-97, the high chemical reactivity of Ru, the potential antitumor activity of several Ru coordination compounds, and BLIP production of Ru-97, provide a unique combination for the application of this isotope in nuclear oncology. A systematic study was undertaken on the synthesis, characterization, and evaluation of a number of ruthenium-labeled compounds. In a variety of animal tumor models, several compounds show considerable promise as tumor-localizing agents when compared to gallium-67 citrate. The compounds studied (with Ru in different oxidation states) include ionic Ru, a number of hydrophilic and lipophilic chelates, and various ammine derivatives

  20. Evaluation Indicator System for China’s Agricultural Industrial Safety

    Institute of Scientific and Technical Information of China (English)

    Qingpeng; GAO; Bin; CHEN; Qinyang; LI

    2013-01-01

    On the basis of new characteristics and trend of China’s agricultural development in the post-WTO period,combining analysis of factors influencing agricultural industrial safety,this paper builds an evaluation indicator system for China’s agricultural industrial safety by scientific indicator system design method.This indicator system includes risk factor indicators(showing risk degree)and capacity factor indicators(showing guaranteeing ability),and consists of 7 subsystems:consumption safety,production safety,industrial controlling capacity,industrial development capacity,industrial development environment,government functions and industrial foundation condition.Risk factor is divided into 5 levels:higher risk,high risk,medium risk,low risk and lower risk;guarantee risk is also divided into five levels:strong,healthy,normal,weak and disabled.According to the overall evaluation score obtained from weighting sum,the agricultural industrial safety includes 5 types:very safe,safe,basically safe,not safe and hazardous.This evaluation indicator system is expected to providing theoretical reference for evaluating China’s agricultural industrial safety.

  1. Safety evaluation of a hydrogen fueled transit bus

    Energy Technology Data Exchange (ETDEWEB)

    Coutts, D.A.; Thomas, J.K.; Hovis, G.L.; Wu, T.T. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1997-12-31

    Hydrogen fueled vehicle demonstration projects must satisfy management and regulator safety expectations. This is often accomplished using hazard and safety analyses. Such an analysis has been completed to evaluate the safety of the H2Fuel bus to be operated in Augusta, Georgia. The evaluation methods and criteria used reflect the Department of Energy`s graded approach for qualifying and documenting nuclear and chemical facility safety. The work focused on the storage and distribution of hydrogen as the bus motor fuel with emphases on the technical and operational aspects of using metal hydride beds to store hydrogen. The safety evaluation demonstrated that the operation of the H2Fuel bus represents a moderate risk. This is the same risk level determined for operation of conventionally powered transit buses in the United States. By the same criteria, private passenger automobile travel in the United States is considered a high risk. The evaluation also identified several design and operational modifications that resulted in improved safety, operability, and reliability. The hazard assessment methodology used in this project has widespread applicability to other innovative operations and systems, and the techniques can serve as a template for other similar projects.

  2. Synthesis and evaluation of new protecting agents against ionizing radiations

    International Nuclear Information System (INIS)

    This thesis is devoted to the synthesis of new pulvinic acid derivatives and the evaluation of their antioxidant and radioprotective properties. This study has been conducted with the aim to develop new protecting agents against ionizing radiations. A new access to pulvinic acid derivatives was developed starting from L-dimethyl tartrate. It is based on a Dieckmann cyclization a dehydration and a Suzuki-Miyaura coupling. It allows a short effective preparation of various pulvinic acid derivatives: tetronic acid derivatives, mono-substituted pulvinic acid derivatives and methyl pulvinates. A modified method has been used to prepare pulvinones. This strategy gave access in four steps to the desired pulvinones. The rapidity of this method is provided by a tandem process, carried out in the final step, involving a Dieckmann cyclization and a β-elimination. A synthesis of 3-aryltetramic acids has also been developed in order to prepare nitrogen derivatives of pulvinic acid. The antioxidant activity of the prepared compounds was then evaluated using various tests: DPPH, ABTS, protection of thymidine and DNA study of lipid peroxidation. These evaluations allowed to define interesting structure-activity relationships of pulvinic derivatives. They have shown that several derivatives have very good antioxidant activities. Finally, radioprotective tests on TK6 cells and mice have have been performed on selected compounds. (author)

  3. Subjective Performance Evaluations, Self-esteem, and Ego-threats in Principal-agent Relations

    DEFF Research Database (Denmark)

    Sebald, Alexander Christopher; Walzl, Markus

    find that agents sanction whenever the feedback of principals is below their subjective self-evaluations even if the agents' payoff is independent of the principals' feedback. Based on our experimental analysis we propose a principal-agent model with subjective performance evaluations that accommodates...

  4. 77 FR 32146 - Safety Evaluation Report, International Isotopes Fluorine Products, Inc., Fluorine Extraction...

    Science.gov (United States)

    2012-05-31

    ... summary, radiation protection, nuclear criticality safety, chemical process safety, fire safety, emergency... COMMISSION Safety Evaluation Report, International Isotopes Fluorine Products, Inc., Fluorine Extraction Process and Depleted Uranium Deconversion Plan, Lea County, NM AGENCY: Nuclear Regulatory...

  5. Status of the international criticality safety benchmark evaluation project (ICSBEP)

    International Nuclear Information System (INIS)

    Since ICNC'99, four new editions of the International Handbook of Evaluated Criticality Safety Benchmark Experiments have been published. The number of benchmark specifications in the Handbook has grown from 2157 in 1999 to 3073 in 2003, an increase of nearly 1000 specifications. These benchmarks are used to validate neutronics codes and nuclear cross-section data. Twenty evaluations representing 192 benchmark specifications were added to the Handbook in 2003. The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is provided in this paper along with a summary of the newly added benchmark specifications that appear in the 2003 Edition of the Handbook. (author)

  6. Evaluation of atmospheric dispersion/consequence models supporting safety analysis

    International Nuclear Information System (INIS)

    Two DOE Working Groups have completed evaluation of accident phenomenology and consequence methodologies used to support DOE facility safety documentation. The independent evaluations each concluded that no one computer model adequately addresses all accident and atmospheric release conditions. MACCS2, MATHEW/ADPIC, TRAC RA/HA, and COSYMA are adequate for most radiological dispersion and consequence needs. ALOHA, DEGADIS, HGSYSTEM, TSCREEN, and SLAB are recommended for chemical dispersion and consequence applications. Additional work is suggested, principally in evaluation of new models, targeting certain models for continued development, training, and establishing a Web page for guidance to safety analysts

  7. An Evaluation Tool for Agricultural Health and Safety Mobile Applications.

    Science.gov (United States)

    Reyes, Iris; Ellis, Tammy; Yoder, Aaron; Keifer, Matthew C

    2016-01-01

    As the use of mobile devices and their software applications, or apps, becomes ubiquitous, use amongst agricultural working populations is expanding as well. The smart device paired with a well-designed app has potential for improving workplace health and safety in the hands of those who can act upon the information provided. Many apps designed to assess workplace hazards and implementation of worker protections already exist. However, the abundance and diversity of such applications also presents challenges regarding evaluation practices and assignation of value. This is particularly true in the agricultural workspace, as there is currently little information on the value of these apps for agricultural safety and health. This project proposes a framework for developing and evaluating apps that have potential usefulness in agricultural health and safety. The evaluation framework is easily transferable, with little modification for evaluation of apps in several agriculture-specific areas. PMID:27494309

  8. Expert evaluation in NPP safety important systems licensing process

    International Nuclear Information System (INIS)

    Expert evaluation of nuclear power plant safety important systems modernization is an integral part of these systems licensing process. The paper contains some aspects of this evaluation which are based on Ukrainian experience of VVER-1000 and VVER-440 modernization. (authors)

  9. The Evaluation of the Safety Benefits of Combined Passive and On-Board Active Safety Applications

    OpenAIRE

    Page, Yves; Cuny, Sophie; Zangmeister, Tobias; Kreiss, Jens-Peter; HERMITTE, Thierry

    2009-01-01

    One of the objectives of the European TRACE project (TRaffic Accident Causation in Europe, 2006–2008) was to estimate the proportion of injury accidents that could be avoided and/or the proportion of injury accidents where the severity could be mitigated for on-the-market safety applications, if 100 % of the car fleet would be equipped with them. We have selected for evaluation the Electronic Stability Control (ESC) and the Emergency Brake Assist (EBA) applications. As for passive safety syst...

  10. Efficacy and Safety of Antifibrinolytic Agents in Reducing Perioperative Blood Loss and Transfusion Requirements in Scoliosis Surgery: A Systematic Review and Meta-Analysis.

    Directory of Open Access Journals (Sweden)

    Meng Wang

    Full Text Available Routine use of antifibrinolytic agents in spine surgery is still an issue of debate.To gather scientific evidence for the efficacy and safety of antifibrinolytic agents including aprotinin, tranexamic acid (TXA and epsilon aminocaproic acid (EACA, traditionally known as Amicar in reducing perioperative blood loss and transfusion requirements in scoliosis surgery.We conducted a systematic review and meta-analysis for randomized controlled trials (RCTs, retrospective case-control studies, and retrospective cohort studies on the use of antifibrinolytic agents in scoliosis surgery by searching in the MEDLINE and EMBASE databases and the Cochrane Database of Systematic Reviews and Controlled Trials of papers published from January 1980 through July 2014. Safety of the antifibrinolytic agents was evaluated in all included studies, while efficacy was evaluated in RCTs.Eighteen papers with a total of 1,158 patients were eligible for inclusion in this study. Among them, 8 RCTs with 450 patients were included for evaluation of pharmacologic efficacy (1 RCT was excluded because of a lack of standard deviation data. Mean blood loss was reduced in patients with perioperative use of antifibrinolytic agents by 409.25 ml intraoperatively (95% confidence interval [CI], 196.57-621.94 ml, 250.30 ml postoperatively (95% CI, 35.31-465.30, and 601.40 ml overall (95% CI, 306.64-896.16 ml. The mean volume of blood transfusion was reduced by 474.98 ml (95% CI, 195.30-754.67 ml. The transfusion rate was 44.6% (108/242 in the patients with antifibrinolytic agents and 68.3% (142/208 in the patients with placebo. (OR 0.38; 95% CI; 0.25-0.58; P<0.00001, I2 = 9%. All studies were included for evaluation of safety, with a total of 8 adverse events reported overall (4 in the experimental group and 4 in the control group.The systematic review and meta-analysis indicated that aprotinin, TXA, and EACA all significantly reduced perioperative blood loss and transfusion requirements

  11. Evaluation of surgical nurses’ attitudes concerning patient safety

    Directory of Open Access Journals (Sweden)

    Ali Şahin

    2015-06-01

    Full Text Available The present study was designed as a descriptive study to evaluate the attitudes of surgical nurses concerning patient safety. The study included 123 nurses, who have been working in the operating rooms of the hospitals in Karaman, Konya for at least one year and were voluntary to participate in the study. Data collection tools included a questionnaire to inquire demographic characteristics of surgical nurses, and “Safety Attitudes Questionnaire (SAQ -Operating Room Version” to evaluate their attitudes concerning patient safety. The mean scores obtained from SAQ sub-dimensions were between 42.12 ±16.82 and 69.07±24.44, whereas the mean score of SAQ total was 59.11 ±13.29. Statistically significant difference was determined between the mean SAQ total score and age, weekly working hours, duration of working in the operating room, resting status, receiving in service training, and training about patient safety. The present study will enhance patient safety in operating rooms by providing an improvement in communication among health workers and in team collaboration, regulating working hours, and scheduling training programs to establish an opinion about worker safety and patient safety.

  12. Agitator tank device and drag reduction agent evaluation

    Institute of Scientific and Technical Information of China (English)

    张帆; 肖博元; 汤养浩; 罗旗荣

    2008-01-01

    The device that consists of tank and disk agitator for evaluation drag reduction agents(DRA) was established.The effect of DRA was defined by testing the changes of agitator torque that drives the disk rotation.The HG-DRA for oil pipeline from Linyi to Puyang was studied by agitator tank device.The relationships between the drag reduction rate and Reynolds number,concentration,balance time were studied.The best concentration and the highest Renords number for the best drag reduction rate were confirmed.The results show that the drag reduction rate tested in agitator tank is close to that in pipeline.The maximum error of drag reduction rate between pipeline and agitator tank is 18.3%,which indicates that the agitator tank device is available to evaluate the effect of DRA for pipeline and it also has the advantages of simple,easy to be operated and using small volume of oil.Those are very helpful for operaters to know the properties of DRA and operate pipeline well.

  13. Safety indicators as a tool for operational safety evaluation of nuclear power plants

    International Nuclear Information System (INIS)

    Performance indicators have found a wide use in the conventional and nuclear industries. For the conventional industry, the goal is to optimize production, reducing loss of time with accidents, human error and equipment downtimes. In the nuclear industry, nuclear safety is an additional goal. This paper presents a general methodology to the establishment, selection and use of safety indicators for a two loop PWR plant, as Angra 1. The use of performance indicators is not new. The NRC has its own methodology and the IAEA presents methodology suggestions, but there is no detailed documentation about indicators selection, criteria and bases used. Additionally, only the NRC methodology performs a limited integrated evaluation. The study performed identifies areas considered critical for the plant operational safety. For each of these areas, strategic sub-areas are defined. For each strategic sub-area, specific safety indicators are defined. These proposed Safety Indicators are based on the contribution to risk considering a quantitative risk analysis. For each safety indicator, a goal, a bounded interval and proper bases are developed, to allow for a clear and comprehensive individual behavior evaluation. On the establishment of the intervals and boundaries, a probabilistic safety study, operational experience, international and national standards and technical specifications were used. Additionally, an integrated evaluation of the indicators, using expert systems, was done to obtain an overview of the plant general safety. This evaluation uses well-defined and clear rules and weights for each indicator to be considered. These rules were implemented by means of a computational language, on a friendly interface, so that it is possible to obtain a quick response about operational safety. This methodology can be used to identify situations where the plant safety is challenged, by giving a general overview of the plant operational condition. Additionally, this study can

  14. Electron beam radiation of resin luting agents - a cytotoxic evaluation

    International Nuclear Information System (INIS)

    The aim of this study was to evaluate and compare the cytotoxicity of three resin luting agents rely x luting cement, rely x luting 2 cement, and clearfil SA luting agent on human dental pulp cells before and after electron beam irradiation. Growth and maintenance of cell cultures of human pulp cells was done in Dulbecco's modified Eagle's Medium (DMEM). The test samples were divided into two categories based on radiation exposure, irradiated category and non-radiated category. Samples in Irradiated category were exposed to electron beam radiation after dose standardisation (Microtron, Electron Beam Accelerator, Microtron Centre, Mangalore University). The dose of radiation used was 200 Gy. Two subgroups of radiated category were made. In 1st sub-group (containing 18 samples), all the 3 luting cements will be placed in sterile packets and irradiated without mixing the two components. In 2nd sub-group (containing 18 samples), all the 3 luting cements will be mixed separately, placed in sterile packets and exposed to electron-beam radiations. Samples in non radiated category were also made 2 groups. In 1st sub-group (containing 18 samples), all the 3 luting cements will be placed in sterile teflon moulds and kept in a humid chamber at 37℃ without mixing the two components. In 2nd sub-group (containing 18 samples), all the 3 the luting cements will be mixed separately, placed in sterile teflon moulds and kept in a humid chamber at 37℃. All the samples were subjected to MTT assay and spectrophotometric analysis and their cytotoxicity was assessed. (author)

  15. Reactor safety; Description and evaluation of safety activities in Nordic countries

    International Nuclear Information System (INIS)

    The report gives a description of safety activities in the nuclear power industry. The study has been carried out as a part of the four year programme in Nordic Safety Research (NKS) which was completed in 1997. The objective of the NKS/RAK-1.1 project 'A survey and an evaluation of safety activities in nuclear power' was to make a broad description of various activities important for safety and to make an assessment of their efficiency. A special consideration was placed on a comparison of practices in Finland and Sweden, and between their nuclear utilities. The study has been divided into two parts, one theoretical part in which a model of the relationships between various activities important for safety has been constructed and one practical part where a total of 62 persons have been interviewed at the authorities, the nuclear utilities and one reactor vendor. To restrict the amount of work two activities, safety analysis and experience feedback, were selected. A few cases connected to incidents at nuclear power plants were discussed in more detail. The report has been structured around a simple model of nuclear safety consisting of the concepts of goals, means and outcomes. This model illustrates the importance of goal formulation, systematic planning and feedback of operational experience as major components in nuclear safety. In assessing organisation and management at authorities and the power utilities there is a clear trend of decentralisation and delegation of authority. The general impression from the study is that the safety activities in Finland and Sweden are efficient and well targeted. The experience from the methodology is favourable and the comparison of practices gives a good ground for a discussion of contents and targeting of safety activities. (EG) activities. (EG)

  16. The International Criticality Safety Benchmark Evaluation Project (ICSBEP)

    International Nuclear Information System (INIS)

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organisation for Economic Cooperation and Development (OECD) - Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Israel, Spain, and Brazil are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled 'International Handbook of Evaluated Criticality Safety Benchmark Experiments.' The 2003 Edition of the Handbook contains benchmark model specifications for 3070 critical or subcritical configurations that are intended for validating computer codes that calculate effective neutron multiplication and for testing basic nuclear data. (author)

  17. Aging evaluation methodology of periodic safety review in Korea

    International Nuclear Information System (INIS)

    In Korea plant lifetime management (PLIM) study for Kori Unit 1 has been performed since 1993. Meanwhile, periodic safety review (PSR) for all operating nuclear power plants (NPPs) has been started with Kori Unit 1 since 2000 per IAEA recommendation. The evaluation period is 10 years, and safety (evaluation) factors are 11 per IAEA guidelines as represented in table 1. The relationship between PSR factors and PLIM is also represented. Among these factors evaluation of 'management of aging' is one of the most important and difficult factor. This factor is related to 'actual condition of the NPP', 'use of experience from other nuclear NPPs and of research findings', and 'management of aging'. The object of 'management of aging' is to obtain plant safety through identifying actual condition of system, structure and components (SSCs) and evaluating aging phenomena and residual life of SSCs using operating experience and research findings. The paper describes the scope and procedure of valuation of 'management of aging', such as, screening criteria of SSCs, Code and Standards, evaluation of SSCs and safety issues as represented. Evaluating SSCs are determined using final safety analysis report (FSAR) and power unit maintenance system for Nuclear Ver. III (PUMAS/N-III). The screening criteria of SSCs are safety-related items (quality class Q), safety-impact items (quality class T), backfitting rule items (fire protection (10CFR50.48), environmental qualification (10CFR50.49), pressurized thermal shock (10CFR50.61), anticipated transient without scram (10CFR50.62), and station blackout (10CFR50.63)) and regulating authority requiring items[1∼3]. The purpose of review of Code and Standards is identifying actual condition of the NPP and evaluating aging management using effective Code and Standards corresponding to reactor facilities. Code and Standards is composed of regulating laws, FSAR items, administrative actions, regulating actions, agreement items, and other

  18. Application of remote sensing image interpretation in seismic safety evaluation

    Science.gov (United States)

    Li, Feng; Wei, Wen-xia; Wang, Gang

    2005-10-01

    As one of essential design gist in important engineering projects, the seismic safety evaluation on choosing engineering site has been applied widely. Using remote sensing images, the analysis to regional seismotectonic environment can bring macroscopic, integrative, dynamic and high efficiency information, so the application of remote sensing technology in seismic safety evaluation of engineering site has fine prospect and will bring great benefit. In this paper, based on remote sensing interpretation to Landsat7 ETM images, also using GIS and field geological investigations, as a case study in Qingdao City, we analyze the physiognomy environment, new tectonic movement, faults activities, and the distributing of deleterious geological objects around the site. Then we find this method can provide good basic geological information for seismic safety evaluation.

  19. International Criticality Safety Benchmark Evaluation Project (ICSBEP) - ICSBEP 2015 Handbook

    International Nuclear Information System (INIS)

    The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy (DOE). The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Nuclear Energy Agency (NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirements and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross-section data. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span approximately 69000 pages and contain 567 evaluations with benchmark specifications for 4874 critical, near-critical or subcritical configurations, 31 criticality alarm placement/shielding configurations with multiple dose points for each, and 207 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications. New to the handbook are benchmark specifications for neutron activation foil and thermoluminescent dosimeter measurements performed at the SILENE critical assembly in Valduc, France as part of a joint venture in 2010 between the US DOE and the French Alternative Energies and Atomic Energy Commission (CEA). A photograph of this experiment is shown on the front cover. Experiments that are found unacceptable for use as criticality safety benchmark experiments are discussed in these

  20. Evaluation of seismic hazards for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    The main objective of this Safety Guide is to provide recommendations on how to determine the ground motion hazards for a plant at a particular site and the potential for surface faulting, which could affect the feasibility of construction and safe operation of a plant at that site. The guidelines and procedures presented in this Safety Guide can appropriately be used in evaluations of site suitability and seismic hazards for nuclear power plants in any seismotectonic environment. The probabilistic seismic hazard analysis recommended in this Safety Guide also addresses the needs for seismic hazard analysis of external event PSAs conducted for nuclear power plants. Many of the methods and processes described may also be applicable to nuclear facilities other than power plants. Other phenomena of permanent ground displacement (liquefaction, slope instability, subsidence and collapse) as well as the topic of seismically induced flooding are treated in Safety Guides relating to foundation safety and coastal flooding. Recommendations of a general nature are given in Section 2. Section 3 discusses the acquisition of a database containing the information needed to evaluate and address all hazards associated with earthquakes. Section 4 covers the use of this database for construction of a seismotectonic model. Sections 5 and 6 review ground motion hazards and evaluations of the potential for surface faulting, respectively. Section 7 addresses quality assurance in the evaluation of seismic hazards for nuclear power plants

  1. FFTF railroad tank car Safety Evaluation for Packaging

    International Nuclear Information System (INIS)

    This Safety Evaluation for Packaging (SEP) provides evaluations considered necessary to approve transfer of the 8,000 gallon Liquid Waste Tank Car (LWTC) from Fast Flux Test Facility (FFTF) to the 200 Areas. This SEP will demonstrate that the transfer of the LWTC will provide an equivalent degree of safety as would be provided by packages meeting U.S. Department of Transportation (DOT) requirements. This fulfills onsite transportation requirements implemented in the Hazardous Material Packaging and Shipping, WHC-CM-2-14

  2. Application of Fisher Discriminant Analysis in Safety Evaluation

    Directory of Open Access Journals (Sweden)

    ZHU XiaoZhen

    2016-06-01

    Full Text Available The multivariate statistical method of Fisher discriminant analysis is applied to safety evaluation, through the analysis of the original data, the assessment process, built up to reflect the evaluated object security status of evaluation function model, so as to simplify the subsequent similar evaluation target workload. The two mine in south of a mining enterprise subordinate to the environmental conditions in six integrated index evaluation, comprehensive index function model is established, finally, the Fisher discrimination obtained results with Bayesian discriminant obtained results, the correctness of the model is verified that the model reliability is high, and simple and practical.

  3. Preliminary safety evaluation of the advanced burner test reactor.

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, F. E.; Fanning, T. H.; Cahalan, J. E.; Nuclear Engineering Division

    2006-09-15

    Results of a preliminary safety evaluation of the Advanced Burner Test Reactor (ABTR) pre-conceptual design are reported. The ABTR safety design approach is described. Traditional defense-in-depth design features are supplemented with passive safety performance characteristics that include natural circulation emergency decay heat removal and reactor power reduction by inherent reactivity feedbacks in accidents. ABTR safety performance in design-basis and beyond-design-basis accident sequences is estimated based on analyses. Modeling assumptions and input data for safety analyses are presented. Analysis results for simulation of simultaneous loss of coolant pumping power and normal heat rejection are presented and discussed, both for the case with reactor scram and the case without reactor scram. The analysis results indicate that the ABTR pre-conceptual design is capable of undergoing bounding design-basis and beyond-design-basis accidents without fuel cladding failures. The first line of defense for protection of the public against release of radioactivity in accidents remains intact with significant margin. A comparison and evaluation of general safety design criteria for the ABTR conceptual design phase are presented in an appendix. A second appendix presents SASSYS-1 computer code capabilities and modeling enhancements implemented for ABTR analyses.

  4. Safety evaluation studies: Sissiboo River Hydro System, Nova Scotia

    International Nuclear Information System (INIS)

    Safety evaluation studies of hydraulic structures are becoming an integral part of the operation and maintenance programs for dam owners in Canada. The Nova Scotia Power Corporation has commenced a program to conduct dam safety evaluations of all their dams of significant size. The study includes the evaluation of the probable maximum flood (PMF) and its basinwide effects. A description is presented of the Sissiboo River hydroelectric system, evaluation of PMF and basinwide flood studies including probable maximum precipitation and a basin simulation model, selection of the inflow design flood, and site-specific evaluations including site inspection, geotechnical investigation, and stability analysis. Recommended remedial works for Sissiboo developments are presented. 14 refs., 2 figs., 4 tabs

  5. A Safety Analysis Approach to Clinical Workflows: Application and Evaluation

    Directory of Open Access Journals (Sweden)

    Lamis Al-Qora’n

    2014-11-01

    Full Text Available Clinical workflows are safety critical workflows as they have the potential to cause harm or death to patients. Their safety needs to be considered as early as possible in the development process. Effective safety analysis methods are required to ensure the safety of these high-risk workflows, because errors that may happen through routine workflow could propagate within the workflow to result in harmful failures of the system’s output. This paper shows how to apply an approach for safety analysis of clinical workflows to analyse the safety of the workflow within a radiology department and evaluates the approach in terms of usability and benefits. The outcomes of using this approach include identification of the root causes of hazardous workflow failures that may put patients’ lives at risk. We show that the approach is applicable to this area of healthcare and is able to present added value through the detailed information on possible failures, of both their causes and effects; therefore, it has the potential to improve the safety of radiology and other clinical workflows.

  6. Safety analysis and evaluation methodology for fusion systems

    International Nuclear Information System (INIS)

    Fusion systems which are under development as future energy systems have reached a stage that the break even is expected to be realized in the near future. It is desirable to demonstrate that fusion systems are well acceptable to the societal environment. There are three crucial viewpoints to measure the acceptability, that is, technological feasibility, economy and safety. These three points have close interrelation. The safety problem is more important since three large scale tokamaks, JET, TFTR and JT-60, start experiment, and tritium will be introduced into some of them as the fusion fuel. It is desirable to establish a methodology to resolve the safety-related issues in harmony with the technological evolution. The promising fusion system toward reactors is not yet settled. This study has the objective to develop and adequate methodology which promotes the safety design of general fusion systems and to present a basis for proposing the R and D themes and establishing the data base. A framework of the methodology, the understanding and modeling of fusion systems, the principle of ensuring safety, the safety analysis based on the function and the application of the methodology are discussed. As the result of this study, the methodology for the safety analysis and evaluation of fusion systems was developed. New idea and approach were presented in the course of the methodology development. (Kako, I.)

  7. A Guidebook for Evaluating Organizations in the Nuclear Industry - an example of safety culture evaluation

    International Nuclear Information System (INIS)

    Organizations in the nuclear industry need to maintain an overview on their vulnerabilities and strengths with respect to safety. Systematic periodical self assessments are necessary to achieve this overview. This guidebook provides suggestions and examples to assist power companies but also external evaluators and regulators in carrying out organizational evaluations. Organizational evaluation process is divided into five main steps. These are: 1) planning the evaluation framework and the practicalities of the evaluation process, 2) selecting data collection methods and conducting the data acquisition, 3) structuring and analysing the data, 4) interpreting the findings and 5) reporting the evaluation results with possible recommendations. The guidebook emphasises the importance of a solid background framework when dealing with multifaceted phenomena like organisational activities and system safety. The validity and credibility of the evaluation stem largely from the evaluation team's ability to crystallize what they mean by organization and safety when they conduct organisational safety evaluations - and thus, what are the criteria for the evaluation. Another important and often under-considered phase in organizational evaluation is interpretation of the findings. In this guidebook a safety culture evaluation in a Nordic nuclear power plant is presented as an example of organizational evaluation. With the help of the example, challenges of each step in the organizational evaluation process are described. Suggestions for dealing with them are presented. In the case example, the DISC (Design for Integrated Safety culture) model is used as the evaluation framework. The DISC model describes the criteria for a good safety culture and the organizational functions necessary to develop a good safety culture in the organization

  8. Reliability evaluation of communication network switching scheme for safety systems

    International Nuclear Information System (INIS)

    To develop the communication network architecture of a safety system of nuclear power plant, the five essence in the design requirements of a communication network for safety-critical systems are determined such as status based architecture, deterministic scheme, separation and isolation, high reliability, verification and validation. In this paper, the data communication network switching scheme for safety systems is proposed based on the circuit switched network with time division multiplexing bus technology considered adequate to the essence of the design requirements and the design elements. The proposed communication network switching scheme was applied to the network design of the SMART protection system, and the reliability was evaluated with the data of components failure rates to determine the applicability of the proposed switching scheme. The proposed switching scheme will be applied as basic communication network architecture of safety system

  9. A Methodology to Evaluate Agent Oriented Software Engineering Techniques

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Chia-En [University of North Texas; Kavi, Krishna M. [University of North Texas; Sheldon, Frederick T [ORNL; Daley, Kristopher M [ORNL; Abercrombie, Robert K [ORNL

    2007-01-01

    Systems using software agents (or multi-agent systems, MAS) are becoming more popular within the development mainstream because, as the name suggests, an agent aims to handle tasks autonomously with intelligence. To benefit from autonomous control and reduced running costs, system functions are performed automatically. Agent-oriented considerations are being steadily accepted into the various software design paradigms. Agents may work alone, but most commonly, they cooperate toward achieving some application goal(s). MAS's are components in systems that are viewed as many individuals living in a society working together. From a SE perspective, solving a problem should encompass problem realization, requirements analysis, architecture design and implementation. These steps should be implemented within a life-cycle process including testing, verification, and reengineering to proving the built system is sound. In this paper, we explore the various applications of agent-based systems categorized into different application domains. A baseline is developed herein to help us focus on the core of agent concepts throughout the comparative study and to investigate both the object-oriented and agent-oriented techniques that are available for constructing agent-based systems. In each respect, we address the conceptual background associated with these methodologies and how available tools can be applied within specific domains.

  10. International handbook of evaluated criticality safety benchmark experiments

    International Nuclear Information System (INIS)

    The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Working Group is to compile critical and subcritical benchmark experiment data into a standardised format that allows criticality safety analysts to easily use the data to validate calculation tools and cross-section libraries. ICSBEP work includes: - Identifying a comprehensive set of critical benchmark data and, to the extent possible, verify the data by reviewing original and subsequently revised documentation, and by talking with the experimenters or individuals who are familiar with the experimenters or the experimental facility; - Evaluating the data and quantify overall uncertainties through various types of sensitivity analysis; - Compiling the data into a standardised format; - Performing calculations of each experiment with standard criticality safety codes; - Formally documenting the work into a single source of verified benchmark critical data. The work of the ICSBEP is documented as an International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook). Currently, the handbook spans nearly 67,000 pages and contains 561 evaluations representing 4839 critical, near-critical, or subcritical configurations, 24 criticality alarm placement/shielding configurations with multiple dose points for each, and 207 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications. The handbook is intended for use by criticality safety analysts to perform necessary validations of their calculational techniques and is expected to be a valuable tool for decades to come. The ICSBEP Handbook is produced in electronic format (pdf files) where the experiments are grouped into evaluations and categorised by: fissile media (plutonium, highly enriched uranium, intermediate and mixed enrichment uranium, low enriched uranium, uranium-233, mixed plutonium-uranium and special isotope systems

  11. Development of evaluation method for software safety analysis techniques

    International Nuclear Information System (INIS)

    Full text: Full text: Following the massive adoption of digital Instrumentation and Control (I and C) system for nuclear power plant (NPP), various Software Safety Analysis (SSA) techniques are used to evaluate the NPP safety for adopting appropriate digital I and C system, and then to reduce risk to acceptable level. However, each technique has its specific advantage and disadvantage. If the two or more techniques can be complementarily incorporated, the SSA combination would be more acceptable. As a result, if proper evaluation criteria are available, the analyst can then choose appropriate technique combination to perform analysis on the basis of resources. This research evaluated the applicable software safety analysis techniques nowadays, such as, Preliminary Hazard Analysis (PHA), Failure Modes and Effects Analysis (FMEA), Fault Tree Analysis (FTA), Markov chain modeling, Dynamic Flowgraph Methodology (DFM), and simulation-based model analysis; and then determined indexes in view of their characteristics, which include dynamic capability, completeness, achievability, detail, signal/ noise ratio, complexity, and implementation cost. These indexes may help the decision makers and the software safety analysts to choose the best SSA combination arrange their own software safety plan. By this proposed method, the analysts can evaluate various SSA combinations for specific purpose. According to the case study results, the traditional PHA + FMEA + FTA (with failure rate) + Markov chain modeling (without transfer rate) combination is not competitive due to the dilemma for obtaining acceptable software failure rates. However, the systematic architecture of FTA and Markov chain modeling is still valuable for realizing the software fault structure. The system centric techniques, such as DFM and Simulation-based model analysis, show the advantage on dynamic capability, achievability, detail, signal/noise ratio. However, their disadvantage are the completeness complexity

  12. Formulation and Evaluation of Nanocrystals of a Lipid Lowering Agent.

    Science.gov (United States)

    Louis, Dina

    2016-01-01

    Atorvastatin calcium, the lipid lowering agent, is taken as a model drug characterized by poor water solubility and bioavailability. In this study an attempt was made for preparation of nanocrystals using high pressure homogenization. A number of stabilizers were included as well as polymers at different concentrations, and the formulations were homogenized for ten cycles at a pressure of 1000 bars. The obtained nano crystals were evaluated by determining their size, zeta potential, saturated solubility and dissolution rate. Results revealed that Formulation 3, containing (10: 1) drug to sodium lauryl sulphate ratio, possessed the highest saturated solubility and dissolution rate, and hence was analyzed by X-ray diffraction analysis, differential scanning calorimetry, Fourrier transform infrared spectroscopy and scanning electron microscopy. An in-vivo study was carried out on the successful formulation in comparison to drug powder using rats as experimental animals. A significant increase in the area under the concentration-time curve Cpmax and MRT for nanocrystals was observed in comparison to the untreated atorvastatin calcium. PMID:27610148

  13. Radiochemical evaluation of a new brain receptor imaging agent

    International Nuclear Information System (INIS)

    We report about the radiochemical evaluation of a new serotonin-1A (5-HT1A) receptor imaging agent. The new derivative of WAY 100635, viz. C1-(2 methoxyphenyl)-(4- mercaptoethyl)-piperazine, was labelled with technetium-99m using thiocresol through 99mTc(V)-glucoheptonate precursor. The labelling was carried out at room temperature within 10 minutes using 370-740 MBq of 99mTc-pertechnetate. The specific activity of the '2+1+1' mixed ligand complex was about 40 GBq/ml. The labelling efficiency and the stability of the labelled compound were monitored by ITLC-SG, solvent extraction and reverse-phase HPLC. The labelling efficiency exceeded 95% and remained high about 4 hours if stored at room temperature or in a refrigerator at 4 deg C. The results give evidence of a high labelling efficiency and stability of the ligand used. The labelled ligand seems to hold promise within the family of existing radiopharmaceuticals

  14. Evaluation of the Finnish nuclear safety research program 'SAFIR2010'

    International Nuclear Information System (INIS)

    A panel of three members has been asked by the Ministry of Employment and the Economy (MEE) to evaluate SAFIR2010, the Finnish research program on nuclear power plant safety. The program was established for the period 2007-2010 to help maintain expertise in nuclear safety, to integrate young people into the research in order to help assure the future availability of expertise, and to support international collaborations. The program is directed by a Steering Group, appointed by MEE, with representatives from all organizations involved with nuclear safety in Finland. SAFIR2010 has consisted of approximately 30 projects from year to year that fall into eight subject areas: 1. Organization and human factors 2. Automation and control room 3. Fuel and reactor physics 4. Thermal hydraulics 5. Severe accidents 6. Structural safety of reactor circuit 7. Construction safety 8. Probabilistic safety analysis (PSA) For each of these areas there are Reference Groups that provide oversight of the projects within their jurisdiction. The panel carried out its evaluation by reviewing copies of relevant documents and, during a one-week period 17-22 January 2010, meeting with key individuals. The results of the panel are provided as general conclusions, responses to questions posed by MEE, challenges and recommendations and comments on specific projects in each subject area. The general conclusions reflect the panel's view that SAFIR2010 is meeting its objectives and carrying out quality research. The questions addressed are: (a.) Are the achieved results in balance with the funding? Are the results exploited efficiently in practice? (b.) How well does the expertise cover the field? Is the entire SAFIR2010 programme balanced to all different fields in nuclear safety? Does it raise efficiently new experts? (c.) Have the 2006 evaluation results been implemented successfully into SAFIR2010 program? (d.) Challenges and recommendations. In general the panel was very positive about SAFIR

  15. Applications of Innovative Safety Analysis Methodology (ISAM) to Reload Safety Evaluation

    International Nuclear Information System (INIS)

    KNF has developed the Innovative Safety Analysis Methodology (ISAM) using RETRAN code for Non-LOCA transient analysis during three years from 2006. The first objective of this project is to secure safety analysis methodology required to the export of X-GEN Fuel which KNF is developing. The second is to set up the improved methodology to be applied to the licensing safety analyses for all the OPR1000 and APR1400 plants. The ISAM possesses the characteristics of a designer-friendly methodology. To verify its applicability to the reload safety evaluation, most transients for safety analysis report and for COLSS/CPC setpoint have been analyzed and compared with current safety analysis results. Comparison results show good agreement between them, and it is concluded that the ISAM can be used in the licensing calculations for all the OPR1000 and APR1400 plants. In this paper, presented are the application results of the transients for COLSS/CPC setpoint such as the single CEA withdrawal (SCEAW) event and the asymmetric steam generator transients (ASGT)

  16. Applications of Innovative Safety Analysis Methodology (ISAM) to Reload Safety Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Chan Su; Um, Kil Sup [Korea Nuclear Fuel, Daejeon (Korea, Republic of)

    2009-05-15

    KNF has developed the Innovative Safety Analysis Methodology (ISAM) using RETRAN code for Non-LOCA transient analysis during three years from 2006. The first objective of this project is to secure safety analysis methodology required to the export of X-GEN Fuel which KNF is developing. The second is to set up the improved methodology to be applied to the licensing safety analyses for all the OPR1000 and APR1400 plants. The ISAM possesses the characteristics of a designer-friendly methodology. To verify its applicability to the reload safety evaluation, most transients for safety analysis report and for COLSS/CPC setpoint have been analyzed and compared with current safety analysis results. Comparison results show good agreement between them, and it is concluded that the ISAM can be used in the licensing calculations for all the OPR1000 and APR1400 plants. In this paper, presented are the application results of the transients for COLSS/CPC setpoint such as the single CEA withdrawal (SCEAW) event and the asymmetric steam generator transients (ASGT)

  17. Safety evaluation of a conceptual fuel recycle complex

    International Nuclear Information System (INIS)

    A conceptual design integration study for an integrated Fuel Recycle Complex (FRC) has been completed. A safety evaluation of the radiation shielding, fire precautions, handling of nonradioactive hazardous materials, criticality hazards, operating errors, and the influence of natural phenomena on the FRC shows that all federal regulations are met or exceeded

  18. Safety evaluation for packaging (onsite) 221 T sodium tanks

    International Nuclear Information System (INIS)

    This safety evaluation for packaging (SEP) allows the transport of approximately 820 kg (1800 lb) of solid sodium between the 200 W Area and the 337 Building in the 300 Area of Hanford to be processed for disposal. This SEP authorizes a one-time shipment

  19. Recommendations for preparing the criticality safety evaluation of transportation packages

    International Nuclear Information System (INIS)

    This report provides recommendations on preparing the criticality safety section of an application for approval of a transportation package containing fissile material. The analytical approach to the evaluation is emphasized rather than the performance standards that the package must meet. Where performance standards are addressed, this report incorporates the requirements of 10 CFR Part 71. 12 refs., 6 figs., 8 tabs

  20. Safety Evaluation for Packaging (onsite) T Plant Canyon Items

    International Nuclear Information System (INIS)

    This safety evaluation for packaging (SEP) evaluates and documents the ability to safely ship mostly unique inventories of miscellaneous T Plant canyon waste items (T-P Items) encountered during the canyon deck clean off campaign. In addition, this SEP addresses contaminated items and material that may be shipped in a strong tight package (STP). The shipments meet the criteria for onsite shipments as specified by Fluor Hanford in HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments

  1. International handbook of evaluated criticality safety benchmark experiments

    International Nuclear Information System (INIS)

    The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Organization for Economic Cooperation and Development - Nuclear Energy Agency (OECD-NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirement and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross section data. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span over 55,000 pages and contain 516 evaluations with benchmark specifications for 4,405 critical, near critical, or subcritical configurations, 24 criticality alarm placement / shielding configurations with multiple dose points for each, and 200 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. Experiments that are found unacceptable for use as criticality safety benchmark experiments are discussed in these evaluations; however, benchmark specifications are not derived for such experiments (in some cases models are provided in an appendix). Approximately 770 experimental configurations are categorized as unacceptable for use as criticality safety benchmark experiments. Additional evaluations are in progress and will be

  2. Evaluation of different cleaning agents used for cleaning ultra tiltration membranes fouled by surface water

    OpenAIRE

    Zondervan, Edwin; Roffel, Brian

    2007-01-01

    This paper reviews the published literature on potential membrane fouling components, available cleaning agents and possible interactions between cleaning agents and fouling components. It also lists the cleaning models available in the literature, and evaluates the advantages and disadvantages of these models. Based on this outcome, a new cleaning model is proposed to capture cleaning dynamics for 10 different cleaning agents, varying from acidic, alkali and oxidizing to sequestering agents ...

  3. Safety and cost evaluation of nuclear waste management

    International Nuclear Information System (INIS)

    The report introduces the results of the nuclear waste management safety and cost evaluation research carried out in the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) during the years 1984-1988. The emphasis is on the description of the state-of-art of performance and cost evaluation methods. The report describes VTT's most important assessment models. Development, verification and validation of the models has largely taken place within international projects, including the Stripa, HYDROCOIN, INTRACOIN, INTRAVAL, PSACOIN and BIOMOVS projects. Furthermore, VTT's other laboratories are participating in the Natural Analogue Working Group,k the CHEMVAL project and the CoCo group. Resent safety analyses carried out in the Nuclear Engineering Laboratory include a concept feasibility study of spent fuel disposal, safety analyses for the Preliminary Safety Analysis Reports (PSAR's) of the repositories to be constructed for low and medium level operational reactor waste at the Olkiluoto and Loviisa power plants as well as safety analyses of disposal of decommissioning wastes. Appendix 1 contains a comprehensive list of the most important publications and technical reports produced. They present the content and results of the research in detail

  4. Triga mark-II,III reactor safety re-evaluation

    International Nuclear Information System (INIS)

    In order to revise safety analysis report of old TRIGA reactors, safety re-evaluation of these reactor was started for necessary parts. This report contains the first year results of the project scheduled for two years. The guide lines of safety re-evaluation was made by translating that of nuclear power plant from the view point of TRIGA reactor confirming the basic safety philosophy as much as possible. First of all, sections of reactor history and comparison with similar reactors are made, since the actual operation records, changes, any modification of similar reactors constructed after then, etc., are realistic and valuable data from the safety aspect of old reactor. For the effectiveness of nuclear analysis, a PC based analysis system using WIMS-D/4 and VENTURE was established, and a program for the natural convection cooling analysis of TRIGA reactor was developed. As a result of thermal-hydraulic analysis it was confirmed that the operation limit of fuel temperature set at 650 deg C without any logical reason is very close to the DNB limit. (Author)

  5. Safety evaluation status report for the prototype license application safety analysis report

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste disposal. The NRC reviewers relied extensively on the Standard Review Plan (SRP), Rev.1 (NUREG-1200), to evaluate the acceptability of the information provided in the EMCB PLASAR. The NRC staff selected certain review areas in the PLASAR for development of safety evaluation report input to provide examples of safety assessments that are necessary as part of a licensing review. Because of the fictitious nature of the assumed disposal site, and the decision to limit the review to essentially first-round review status, the NRC staff report is labeled a ''Safety Evaluation Status Report'' (SESR). Appendix A comprises the NRC review comments and questions on the information that DOE submitted in the PLASAR. The NRC concentrated its review on the design and operations-related portions of the EMCB PLASAR

  6. First investigations on the safety evaluation of smart sensors

    International Nuclear Information System (INIS)

    IPSN (Institute for Protection and Nuclear Safety) is the technical support for the French nuclear safety authority and thus involved in the safety evaluation of new I and C technologies and particularly of smart sensors. Smart sensors are characterized by the use of a microprocessor that converts the process variable into digital signals and exchanges other information with I and C control systems. There are two types of smart sensors: HART (Highway Addressable Remote Transducer) sensors, which provide both analogue (4 to 20 mA) and digital signals, and network sensors, which provide only digital signals. The expected benefits for operators are improved accuracy and reliability and cost savings in installation, commissioning, testing and maintenance. Safety evaluation of these smart sensors raises new issues: How does the sensor react to unknown commands? How to avoid unexpected changes in configuration? What is its sensitivity to electromagnetic interferences (EMI), to radiations...? In order to evaluate whether these sensors can be qualified for a safety application and to define the qualification tests to be done, IPSN has planned some functional and hardware tests (EMI, radiations) on 'HART' and field bus sensors. During the functional tests, we were not able to disrupt the HART tested sensors by invalid commands. However, these results cannot be extended to other sensors, because of the use of different technology, of different versions of hardware and software and of constructors' specific commands. Furthermore, easy modifications of configuration parameters can cause additional failures. Environmental tests are in progress on HART sensors and will be followed by experiments on field bus sensors. These preliminary investigations and the latest incident initiated by an incorrect computing algorithm of digital switchgear at Ringhals NPP, clearly illustrate that testing and verification programmes for smart equipment must be meticulously designed and reviewed

  7. Evaluation of carbamate insecticides as chemotherapeutic agents for cancer

    Directory of Open Access Journals (Sweden)

    Mohd. Amanullah

    2011-01-01

    Full Text Available Background: Cancer chemotherapy has already been in practice by the use of toxins and some of the specific poisonous compounds of cyanide derivatives. Carbamate insecticides inhibit cellular metabolism including energy, protein, and nucleic acid metabolism, thereby, causing cell regression and death. Aim: Preliminary evaluation of three carbamate insecticides, namely, baygon, carbaryl, and carbofuran as chemotherapeutic agents for cancer is undertaken in the present study. Materials and Methods: The toxicity of carbamates on squamous cell carcinoma was assessed in-vitro using dye binding tests. Cells were grown in microtitration ELISA plates, as adherent cultures, for six hours, and then exposed to the drugs for 2, 4, 8, and 12 hours, and finally stained with neutral red, to assess the viable cell number, and with methylene blue for the determination of protein in the monolayer. Optical density was read in an ELISA reader. Statistical Analysis: The data obtained during the experiment was subjected to statistical analysis by using the student ′t′ test. Results: The results indicated that the percentage of the viable cell number reduced with an increase in the time of exposure of the drugs. Exposure of the tumor cells to the drugs for 12 hours detached them completely from the wells, and hence, all the cells were washed out. Exposure of the drugs prior to the establishment of the culture in-vitro resulted in the non-formation of the monolayer in the wells. Conclusions: Among the three drugs studied, the survival percent was least with carbaryl treatment followed by baygon, and with carbofuran treatment it was almost near to control group.

  8. 29 CFR 1960.80 - Secretary's evaluations of agency occupational safety and health programs.

    Science.gov (United States)

    2010-07-01

    ... EMPLOYEE OCCUPATIONAL SAFETY AND HEALTH PROGRAMS AND RELATED MATTERS Evaluation of Federal Occupational Safety and Health Programs § 1960.80 Secretary's evaluations of agency occupational safety and health... evaluating an agency's occupational safety and health program. To accomplish this, the Secretary......

  9. Safety Evaluation Report related to the operation of Hope Creek Generating Station (Docket No. 50-354). Supplement No. 4

    International Nuclear Information System (INIS)

    Supplement No. 4 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company on its own behalf as co-owner and as agent for the other co-owner, the Atlantic City Electric Company, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  10. Safety Evaluation Report related to the operation of Hope Creek Generating Station (Docket No. 50-354)

    International Nuclear Information System (INIS)

    Supplement No. 3 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company on its own behalf as co-owner and as agent for the other co-owner, the Atlantic City Electric Company, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report. 6 tabs

  11. Safety evaluation report related to the operation of Hope Creek Generation Station (Docket No. 50-354). Supplement No. 5

    International Nuclear Information System (INIS)

    Supplement No. 5 to the Safety Evaluation Report on the application filed by Public Service Electric and Gas Company on its own behalf as co-owner and as agent for the other co-owner, the Atlantic City Electric Company, for a license to operate Hope Creek Generating Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Lower Alloways Creek Township in Salem County, New Jersey. This supplement reports the status of certain items that had not been resolved at the time of the publication of the Safety Evaluation Report

  12. Review of SKB's preliminary safety evaluations for Forsmark and Laxemar

    International Nuclear Information System (INIS)

    This report presents SKI's and SSI's review of SKB's preliminary safety evaluations for Forsmark and Laxemar. The purpose of the review is to assess if the extent of SKB's initial site investigations are sufficient and if they are performed with adequate quality and also if they comprise the data that is needed for future safety analysis. To meet the request from the municipalities where site investigations are performed the authorities have also attempted to elucidate if a site has such obvious weakness that it probably will not comply with authority regulations. The target groups for the review are the municipalities in Oskarshamn and Oesthammar, and SKB

  13. Children's Agricultural Safety Network: Evaluating Organizational Effectiveness and Impacts.

    Science.gov (United States)

    Cramer, Mary E; Wendl, Mary J

    2015-01-01

    Coalitions that are effectively organized and led are more likely to achieve their intended program outcomes and impacts, as well as achieve sustainability. External evaluation of the coalition's governance and leadership can help identify strengths and areas for improvement. This article describes the evaluation of the Children's Agricultural Safety Network (CASN)-a national coalition, or network of 45 organizational members. The conceptual framework, Internal Coalition Outcomes Hierarchy, guided the evaluation. We used a mixed-methods approach to answer study's primary objectives from the perspective of CASN members and leaders for (a) organizational effectiveness, (b) network impact, and (c) member benefits. We collected quantitative data using a survey and the Internal Coalition Effectiveness (ICE) instrument. Focused interviews were conducted by phone to gather rich data on examples. Combined findings showed that both members and leaders rated the CASN effective in all construct areas that define successful coalitions. Members feel as invested in CASN success as do leaders. The major impact of CASN has been as a national leader and clearinghouse for childhood safety issues, and the most frequently cited example of impact was the national tractor safety campaign. Members identified the benefits of CASN membership as networking, resource sharing, and opportunities to enhance their knowledge, skills, and practices in the area. Members also valued the national attention that CASN was able to bring to the important issues in childhood agricultural safety. Suggestions for improvement were to focus on more research to improve best practices and strengthen dissemination and implementation science. PMID:25906269

  14. Trial evaluations in comparison with the 1983 safety goals

    International Nuclear Information System (INIS)

    This report provides retrospective comparisons of selected generic regulatory actions to the 1983 NRC safety goals, which had been issued for evaluation during a two-year period. The issues covered are those analyzed by the Office of Nuclear Reactor Regulation (NRR) (assisted in some cases by the Battelle Pacific Northwest Laboratory). The issues include auxiliary feedwater reliability, pressurized thermal shock, power-operated relief valve isolation, asymmetric blowdown loads on PWR primary systems, pool dynamic loads for BWR containments, and steam generator tube rupture. Calculated core-melt frequencies, mortality risks, and cost-benefit ratios are compared with the corresponding safety-goal quantitative design objectives. Considerations that should influence interpretation of the comparisons are discussed. Comments are included on whether and how the safety goals may have helped in the regulatory decision process and on problems encountered

  15. Evaluating Models of Human Performance: Safety-Critical Systems Applications

    Science.gov (United States)

    Feary, Michael S.

    2012-01-01

    This presentation is part of panel discussion on Evaluating Models of Human Performance. The purpose of this panel is to discuss the increasing use of models in the world today and specifically focus on how to describe and evaluate models of human performance. My presentation will focus on discussions of generating distributions of performance, and the evaluation of different strategies for humans performing tasks with mixed initiative (Human-Automation) systems. I will also discuss issues with how to provide Human Performance modeling data to support decisions on acceptability and tradeoffs in the design of safety critical systems. I will conclude with challenges for the future.

  16. Evaluation tool for road safety campaigns – a short overview

    Directory of Open Access Journals (Sweden)

    Marko Divjak

    2011-04-01

    Full Text Available The aim of this paper is to introduce the Evaluation tool for road safety campaigns which is one of the most important results of the CAST project. Recommendations and guidelines of the Evaluation tool are based on the fact that certain attributes (the scope of a campaign, the target group(s, the goals and the activities of a campaign of a campaign have a detrimental effect upon designing evaluation, which means choosing suitable measurement variables, data collection methods/techniques and research designs. Recommendations and guidelines about various options for evaluation are given for each of the four attributes separately. The Evaluation tool guides evaluator through the process by emphasizing the approaches that appear most useful in a given context together with the main strengths and weaknesses.

  17. Fuel Receiving and Storage Station. Nuclear Regulatory Commission's safety evaluation report

    International Nuclear Information System (INIS)

    The safety evaluation report covers design of structures, components, equipment, and systems; nuclear criticality safety; radiological safety; accident analysis; conduct of operations; quality assurance; common defense and security; financial qualifications; financial protection and indemnity requirements; and technical specifications

  18. Road network safety evaluation using Bayesian hierarchical joint model.

    Science.gov (United States)

    Wang, Jie; Huang, Helai

    2016-05-01

    Safety and efficiency are commonly regarded as two significant performance indicators of transportation systems. In practice, road network planning has focused on road capacity and transport efficiency whereas the safety level of a road network has received little attention in the planning stage. This study develops a Bayesian hierarchical joint model for road network safety evaluation to help planners take traffic safety into account when planning a road network. The proposed model establishes relationships between road network risk and micro-level variables related to road entities and traffic volume, as well as socioeconomic, trip generation and network density variables at macro level which are generally used for long term transportation plans. In addition, network spatial correlation between intersections and their connected road segments is also considered in the model. A road network is elaborately selected in order to compare the proposed hierarchical joint model with a previous joint model and a negative binomial model. According to the results of the model comparison, the hierarchical joint model outperforms the joint model and negative binomial model in terms of the goodness-of-fit and predictive performance, which indicates the reasonableness of considering the hierarchical data structure in crash prediction and analysis. Moreover, both random effects at the TAZ level and the spatial correlation between intersections and their adjacent segments are found to be significant, supporting the employment of the hierarchical joint model as an alternative in road-network-level safety modeling as well. PMID:26945109

  19. Microbubble ultrasound contrast agent with three esters and carboxylic methyl cellulose as main shell materials: Its preparation and imaging evaluation

    Institute of Scientific and Technical Information of China (English)

    杜永峰; 万明习; 周晓东

    2003-01-01

    Objective: To study on the preparation process of a new surfactant-based microbubble ultrasound contrast agent and to evaluate its contrast effects in vivo. Methods: Microbubble ultrasound contrast agent with three ester surfactants and other additives as its shell materials was prepared by sonication. Sulfur hexafluoride was adopted as the inner gas of the microbubbles. New methods through the combination of optical microscope and some softwares were used to measure the size distribution and the concentration of the microbubbles. Some parameters such as the pH value of the phosphate buffer, quantity of the carboxylic methyl cellulose in the shell materials, selection of the ultrasound power and process time, were studied. Six hybirded dogs were used to verify the in vivo contrast imaging of the contrast agent using second harmonic power Doppler modality. Safety and persistent time of the agent inner animal body were also investigated. Results: Ultrasound contrast agent prepared in the experiment had an average microbubble diameter of 3.95 microns with concentration of 3.6×109 microbubbles per millilitre. Carboxylic methyl cellulose was found as an important shell material which had obviously effect on the microbubble stability and production even with a little quantity. The buffer pH value also had a key role on the microbubble formation and the final production. When the buffer pH value reached 7.4, there was no microbubble produced. Under the approximate microbubble production, process time could be shorten with the increasing ultrasound power. The obvious ultrasound contrast imaging effects were detected in the dog's heart chamber and liver as well as kidney using only one millilitre agent when diluted. The agent was found safe to the dogs. At the same time, persistent time of the agent was found over 20 min in the dog's body. Conclusion: The new ultrasound contrast agent prepared in the experiment has high microbubble production and concentration, narrow

  20. Safety Evaluation for Fourth Core Loading of ETRR-2

    International Nuclear Information System (INIS)

    This paper presents the safety evaluation for the fourth for loading of the ETRR-2 and verification of the core neutronic design criteria for fourth core load. the aims of this work are to assure that the core load satisfies all neutronic safety criteria and to evaluate all core neutronic parameters. the calculation line is a combination of cell calculation transport cod WIMSD-4 and core calculation diffusion code (CITVAP). Two set of macroscopic cross section libraries were generated (hot with xenon and cold without xenon) using the cell calculation code WIMSD4 and POS-WIMS program to be used in global reactor calculation . the core calculations are performed using CITVAP code, starting from first core load up to the end of fourth core. these calculations include burn up calculations and verification of the core neutronic safety criteria . the different cores calculations considered the actual load pattern as well as the detailed operation history. comparisons with experimental measurements of actual critical configurations were performed during the different reload history and the results are very closed by that for utility and all neutronic safety criteria are fulfilled , moreover the accuracy of the burnup calculation is very good. the different critical core configurations were correctly predicted with error less than 200 pcm

  1. Taurolidine: cytotoxic and mechanistic evaluation of a novel antineoplastic agent.

    Science.gov (United States)

    Calabresi, P; Goulette, F A; Darnowski, J W

    2001-09-15

    Bis-(1,1-dioxoperhydro-1,2,4-thiadiazinyl-4)methane (taurolidine) is a synthetic broad-spectrum antibiotic that reacts with bacterial cell membrane components to prevent adhesion to epithelial cell surfaces. Reflecting the key role of adhesion in the growth and development of human solid tumors, studies were initiated to assess the antiproliferative activity of this agent in selected human and murine tumor cell lines. A 3-day exposure to Taurolidine inhibited the growth of all of the cell lines evaluated with IC(50)s ranging from 9.6-34.2 microM. Studies to identify the mechanism responsible for this effect were conducted in NIH-3T3 murine fibroblasts and the PA-1 and SKOV-3 human ovarian tumor cells. These studies revealed that a 48-h exposure to taurolidine had little effect on cell cycle distribution in PA-1 and SKOV-3 cells but significantly increased the appearance of DNA debris in the sub-G(0)/G(1) region, an effect consistent with an induction of apoptosis. In contrast, in NIH-3T3 cells, taurolidine exposure did not increase DNA debris in the sub-G(0)/G(1) region. Additional studies assessed phosphotidylserine externalization after a 24-h exposure to taurolidine using annexin-V binding as a cell surface marker. These studies revealed that taurolidine increased the percentage of annexin-V-positive cells by 4-fold and 3-fold in PA-1 and SKOV-3 cells, respectively. In NIH-3T3 cells, taurolidine exposure slightly increased ( approximately 5%) annexin-V binding. Parallel studies revealed that exposure to taurolidine also resulted in poly(ADP-ribose) polymerase cleavage in both ovarian tumor cell lines but not in NIH-3T3 cells. Finally, murine-based studies were conducted to assess the antineoplastic activity of three consecutive daily i.p. bolus injections of taurolidine at doses ranging from 5-mg injection/mouse to 30-mg injection/mouse. The 20-mg injection dose produced approximately 10% mortality and was identified as the maximally tolerated dose in this model

  2. Review on the Evaluation System of Public Safety Carrying Capacity about Small Town Community

    OpenAIRE

    Sun, Ming; Zhu, Tianyu

    2014-01-01

    Recently, small town community public safety problem has been increasingly highlighted, but its research is short on public safety carrying capacity. Through the investigation and study of community public safety carrying capacity, this paper analyzes the problem of community public safety in our country, to construct index evaluation system of public safety carrying capacity in small town community. DEA method is used to evaluate public safety carrying capacity in small town community, to pr...

  3. Applying a realistic evaluation model to occupational safety interventions

    DEFF Research Database (Denmark)

    Pedersen, Louise Møller

    2016-01-01

    characteristics of key actors (defined mechanisms), and the interplay between them, and can be categorized as expected or unexpected. However, little is known about ’how’ to include context and mechanisms in evaluations of intervention effectiveness. A revised realistic evaluation model has been introduced as a...... method to overcome these challenges. Focus is: What works, for whom, under what circumstances, in what respects, and how? Contextual factors such as underreporting of accidents/injuries and mechanisms, e.g. leader motivation, are included in the model and proposed to be measured using quantitative and...... qualitative methods. This revised model has, however, not been applied in a real life context. Method: The model is applied in a controlled, four-component, integrated behaviour-based and safety culture-based safety intervention study (2008-2010) in a medium-sized wood manufacturing company. The interventions...

  4. On Some Methods in Safety Evaluation in Geotechnics

    Directory of Open Access Journals (Sweden)

    Puła Wojciech

    2015-06-01

    Full Text Available The paper demonstrates how the reliability methods can be utilised in order to evaluate safety in geotechnics. Special attention is paid to the so-called reliability based design that can play a useful and complementary role to Eurocode 7. In the first part, a brief review of first- and second-order reliability methods is given. Next, two examples of reliability-based design are demonstrated. The first one is focussed on bearing capacity calculation and is dedicated to comparison with EC7 requirements. The second one analyses a rigid pile subjected to lateral load and is oriented towards working stress design method. In the second part, applications of random field to safety evaluations in geotechnics are addressed. After a short review of the theory a Random Finite Element algorithm to reliability based design of shallow strip foundation is given. Finally, two illustrative examples for cohesive and cohesionless soils are demonstrated.

  5. Radiological safety evaluation report for NUWAX-79 exercise

    International Nuclear Information System (INIS)

    An analysis of the radiological safety of the NUWAX-79 exercise to be conducted on the Nevada Test Site in April 1979 is given. An evaluation of the radiological safety to the participants is made using depleted uranium (D-38) in mock weapons parts, and 223Ra and its daughters as a radioactive contaminant of equipment and terrain. The radiological impact to offsite persons is also discussed, particularly for people living at Lathrop Wells, Nevada, which is located 7 miles south of the site proposed for the exercise. It is the conclusion of this evaluation that the potential radiological risk of this exercise is very low, and that no individual should receive exposure to radioactivity greater than one-tenth of the level permitted under current federal radiation exposure guidelines

  6. Technical evaluation of seismic qualification of safety-related equipment

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Yang Hui; Park, Heong Gee; Park, Yeong Seok [Univ. of Incheon, Incheon (Korea, Republic of)] (and others)

    1994-04-15

    This study is purposed to evaluate the technical acceptability of the procedures and techniques of seismic qualifications which were performed for the YGN 3 and 4 safety-related equipment.This study is also targeted to suggest a systematized technical procedure guide for the effective performance and review of the seismic qualification, which reflects the most up-to-date licensing requirements and state-of the-art.

  7. Safety evaluation for packaging (onsite) depleted uranium waste boxes

    International Nuclear Information System (INIS)

    This safety evaluation for packaging (SEP) allows the one-time shipment of ten metal boxes and one wooden box containing depleted uranium material from the Fast Flux Test Facility to the burial grounds in the 200 West Area for disposal. This SEP provides the analyses and operational controls necessary to demonstrate that the shipment will be safe for the onsite worker and the public

  8. Using photographic interpretation to evaluate the safety of home environments.

    Science.gov (United States)

    Lehna, Carlee; Twyman, Stephanie; Myers, John

    2016-12-01

    In the US there were 400,000 home fires resulting in 2755 deaths, 12,450 injuries, and $6.9B lost. The purpose of this study was to evaluate the content-validity of photographs taken in the home for use as an educational instrument to teach about "safe" and "unsafe" fire safety practice for adults and older adults. A total of 73 home fire safety experts were provided 27 photographs to evaluate home fire safety practice. Initially, a Krippendorff's alpha was calculated for the first 24 questions to evaluate inter-rater reliability, and differences in demographics were evaluated. Unique codes and themes for the last three questions were identified and inter-rater reliability examined. A majority of respondents were female (n = 43, 60.6%), college educated (n = 61, 83.6%), nurses (n = 25, 33.8%), or worked for a fire department (n = 21, 29.6%). Their mean age was 45.5 years and they had 11.05 years of experience. The first 24 questions had high inter-rater reliability (Krippendorff α = 0.831). No significant differences existed between the strata of the demographic variables (all p-values > 0.05). Similarly, based on the codes and themes identified, the last three questions had moderate-to-good inter-rater reliability (Krippendorff α = 0.764). Providing photographs as a 'seek-and-find' or 'What's wrong with this picture?' tools and simplified visual images is an excellent way to aid recognition of unsafe home fire safety environments. Education through non-traditional visual methods increases the possibility of change for diverse low-literacy populations. PMID:27617192

  9. Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

    International Nuclear Information System (INIS)

    IAEA defined safety culture as follows: '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'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea

  10. Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2015-05-15

    IAEA defined safety culture as follows: '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'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea.

  11. Evaluating network analysis and agent based modeling for investigating the stability of commercial air carrier schedules

    Science.gov (United States)

    Conway, Sheila Ruth

    For a number of years, the United States Federal Government has been formulating the Next Generation Air Transportation System plans for National Airspace System improvement. These improvements attempt to address air transportation holistically, but often address individual improvements in one arena such as ground or in-flight equipment. In fact, air transportation system designers have had only limited success using traditional Operations Research and parametric modeling approaches in their analyses of innovative operations. They need a systemic methodology for modeling of safety-critical infrastructure that is comprehensive, objective, and sufficiently concrete, yet simple enough to be deployed with reasonable investment. The methodology must also be amenable to quantitative analysis so issues of system safety and stability can be rigorously addressed. The literature suggests that both agent-based models and network analysis techniques may be useful for complex system development and analysis. The purpose of this research is to evaluate these two techniques as applied to analysis of commercial air carrier schedule (route) stability in daily operations, an important component of air transportation. Airline-like routing strategies are used to educe essential elements of applying the method. Two main models are developed, one investigating the network properties of the route structure, the other an Agent-based approach. The two methods are used to predict system properties at a macro-level. These findings are compared to observed route network performance measured by adherence to a schedule to provide validation of the results. Those interested in complex system modeling are provided some indication as to when either or both of the techniques would be applicable. For aviation policy makers, the results point to a toolset capable of providing insight into the system behavior during the formative phases of development and transformation with relatively low investment

  12. Evaluation of Seismic Hazards for Nuclear Power Plants. Safety Guide

    International Nuclear Information System (INIS)

    This Safety Guide provides guidelines and recommends procedures for the evaluation of seismic hazards for nuclear power plants. Specifically, it provides recommendations on how to determine the ground motion hazards for a plant at a particular site and the potential for surface faulting, which could affect the feasibility of construction and safe operation of a plant at that site. Contents: 1. Introduction; 2. General recommendations; 3. Necessary information and investigations (database); 4. Construction of a regional seismotectonic model; 5. Evaluation of ground motion hazard; 6. Potential for surface faulting at the site; 7. Quality assurance; Glossary.

  13. TRANSPORTATION CASK RECEIPT/RETURN FACILITY CRITICALITY SAFETY EVALUATIONS

    Energy Technology Data Exchange (ETDEWEB)

    C.E. Sanders

    2005-04-26

    The purpose of this design calculation is to demonstrate that the handling operations of transportation casks performed in the Transportation Cask Receipt and Return Facility (TCRRF) and Buffer Area meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC [Bechtel SAIC Company] 2004 [DIRS 171599], Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''Transportation Cask Receipt/Return Facility Description Document'' (BSC 2004 [DIRS 170217], Section 3.2.3). Specific scope of work contained in this activity consists of the following items: (1) Evaluate criticality effects for both dry and fully flooded conditions pertaining to TCRRF and Buffer Area operations for defense in depth. (2) Evaluate Category 1 and 2 event sequences for the TCRRF as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). This evaluation includes credible fuel reconfiguration conditions. In addition to the scope of work listed above, an evaluation was also performed of modeling assumptions for commercial spent nuclear fuel (CSNF) regarding inclusion of plenum and end regions of the active fuel. This calculation is limited to CSNF and US Department of Energy (DOE) SNF. it should be mentioned that the latter waste form is evaluated more in depth in the ''Canister Handling Facility Criticality Safety Calculations (BSC 2004 [DIRS 167614]). Further, the design and safety analyses of the naval SNF canisters are the responsibility of the US Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the TCRRF and Buffer Area and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will

  14. Evaluation of the Community's nuclear reactor safety research programme

    International Nuclear Information System (INIS)

    This report describes an evaluation of the 1980-85 CEC reactor safety programme prepared, at the invitation of the Commission, by a panel of six independent experts by means of examining the relevant document and by holding hearings with the responsible CEC staff. It contains the recommendations made by the panel on the following topics: the need for the JRC to continue to make its competence in the reactor safety field available to the Community; the importance of continuity in the JRC and shared-cost action programmes; the difficulty of developing reactor safety research programmes which satisfy the needs of users with diverse needs; the monitoring of the utilization of the research results; the maintenance of the JRC computer codes used by the Member States; the spin-off from research results being made available to other industrial sectors; the continued contact between the JRC researchers and the national experts; the coordination of LWR safety research with that of the Member States; and, the JRC work on fast breeders to be planned with regard to the R and D programmes of the Fast Reactor European Consortium

  15. Safety evaluation of rebaudioside A produced by fermentation.

    Science.gov (United States)

    Rumelhard, Mélina; Hosako, Hiromi; Eurlings, Irene M J; Westerink, Walter M A; Staska, Lauren M; van de Wiel, Jeanine A G; La Marta, James

    2016-03-01

    The safety of rebaudioside A, produced fermentatively by Yarrowia lipolytica encoding the Stevia rebaudiana metabolic pathway (fermentative Reb A), is based on several elements: first, the safety of steviol glycosides has been extensively evaluated and an acceptable daily intake has been defined; second, the use of Y. lipolytica, an avirulent yeast naturally found in foods and used for multiple applications; and third the high purity of fermentative Reb A and its compliance with internationally defined specifications. A bacterial reverse mutation assay and an in vitro micronucleus test conducted with fermentative Reb A provide evidence for its absence of mutagenicity, clastogenicity and aneugenicity. The oral administration of fermentative Reb A to Sprague-Dawley rats for at least 91 days did not lead to any adverse effects at consumption levels up to 2057 mg/kg bw/day for males and 2023 mg/kg bw/day for females, which were concluded to be the No Observed Adverse Effect Levels. The results were consistent with outcomes of previous studies conducted with plant-derived rebaudioside A, suggesting similar safety profiles for fermentative and plant-derived rebaudioside A. The results of the toxicity studies reported here support the safety of rebaudioside A produced fermentatively from Y. lipolytica, as a general purpose sweetener. PMID:26776281

  16. A guideline for comprehensive evaluation of a licensee's effort to cultivate safety culture

    International Nuclear Information System (INIS)

    The nuclear industry in Japan had held excellent performance in safety in the world during 90's. However recent events stem from organizational factors and defects of safety culture are pointed out in their contexts. In order to reduce accidents caused by organizational factors, the Japanese Regulatory body NISA (Nuclear and Industrial Safety Agency) decided to evaluate a licensee's effort for the cultivation of safety culture, and to order all licensses to add the provision of cultivating safety culture to their safety preservation rules. The inspection for the new safety preservation rules started in December, 2007. For a measure of evaluation by resident inspectors, NISA and the Japan Nuclear Energy Safety Organization (JNES) prepared a guideline for the prevention of degradation of safety culture and organizational climate. In this guideline, 14 items were defined as the components of the safety culture or as the viewpoints to evaluate the effort made to prevent any degradation of safety culture and organizational climate in the daily safety preservation activities. The 14 items are also used to establish the method to comprehensively evaluate the effort to prevent degradation of safety culture and organizational climate. This method consists of 10 steps: two steps to taken prior to start of the evaluation, two steps to be taken during the evaluation period, 5 steps to be taken during a comprehensive evaluation period and a final step to be taken for comprehensive findings for safety culture. This paper mainly describes the viewpoints to evaluate comprehensively a licensee's effort for cultivation of safety culture. (author)

  17. Safety evaluation review of the prototype license application safety analysis report

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the belowground vault (BGV) alternative method of low-level radioactive waste disposal. In Volume 1 of NUREG-1375, the NRC staff provided the safety review results for an earth-mounded concrete bunker PLASAR. In the current report, the staff focused its review on the design, construction, and operational aspects of the BGV PLASAR. The staff developed review comments and questions using the Standard Review Plan (SRP), Rev. 1 (NUREG-1200) as the basis for evaluating the acceptability of the information provided in the BGV PLASAR. The detailed review comments provided in this report are intended to be useful guidance to facility developers and State regulators in addressing issues likely to be encountered in the review of a license application for a low-level-waste disposal facility. 44 refs

  18. A study on the safety evaluation of concentrated tritium storage

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. J.; Kim, K. K.; Lee, S. Y.; Lee, Y. E.; Hong, D. S.; Jung, H. Y.; Song, M. C.; Hwang, K. H.; Kim, S. I.; Yook, D. S.; Sheen, J. J. [Korea Advanced Institute of Science and Technology, Taejeon (Korea)

    2001-03-01

    In this study, hazards of hydrogen and the risk due to storage of tritium are reviewed. The safety related factors are suggested in terms of classification of hydrogen hazards and problems related to the tritium storage. The major design parameters of the vessel of foreign countries for the storage and transport of tritium are reviewed. By review of major safety parameters related to the tritium storage, the results of this study can be applied and helpful to the development and design of tritium storage vessel in Korea. Also, the results can be useful at design of the tritium treatment facility. The integrity of tritium storage vessel material was evaluated with considering the embrittlement of metal material in hydrogen environment. The tritium storage is one of the most important problems for the safety of tritium removal facility. The research for tritium storage could be divided into two parts, one is for the metal getter of tritium and the other is for the integrity of tritium storage vessel. Especially, the integrity of tritium storage vessel is up to the tritium embrittlement of vessel materials, for tritium vessel is mostly made of metal material. In this work, the evaluation of the tritium embrittlement for the tritium storage vessel material is performed with the equipment that is made for high temperature and high vacuum. 33 refs., 56 figs., 23 tabs. (Author)

  19. Safety Evaluation Report related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report on the application filed by Duquesne Light Company, as applicant and agent for the owners, for a license to operate the Beaver Valley Power Station Unit 2 (Docket No. 50-412) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River. Subject to the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  20. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    The Safety Evaluation Report for the application filed by Northeast Nuclear Energy Company, as applicant and agent for the owners, for a license to operate the Millstone Nuclear Power Station Unit 3 (Docket No. 50-423), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  1. Squale: evaluation criteria of functioning safety; Squale: criteres d`evaluation de la surete de fonctionnement

    Energy Technology Data Exchange (ETDEWEB)

    Deswarte, Y.; Kaaniche, M. [Centre National de la Recherche Scientifique (CNRS), 31 - Toulouse (France). Laboratoire d`Analyse et d`Architecture des Systemes; Corneillie, P. [CE2A-DI, 92 - Courbevoie (France); Benoit, P. [Matra Transport International, 92 - Montrouge (France)

    1998-05-01

    The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.) 15 refs.

  2. Evaluation of CANDU safety-system calibration accuracy through monitoring

    International Nuclear Information System (INIS)

    CANDU operators are increasingly being required to demonstrate that estimated accuracies of the transmitters used to measure process variables in CANDU special safety systems are being achieved in operation. At present, this is done by recalibrating all transmitters periodically, typically every one to three years. Functional checks are performed more frequently. These include panel checks (i.e., visual monitoring and cross-comparison of redundant process measurements) and safety-system process-trip tests (i.e., valving-in test pressures to activate the alarm units). These functional tests provide assurance that transmitters and related circuits are working, but they are not always sufficiently sensitive to evaluate calibration accuracy. Continuous computerized monitoring of safety-system signals is being investigated as one approach to verifying safety-system calibration accuracy and transmitter functionality. Eventually, if successful, it may enable a reduction in the frequency of process trip testing (a labour-intensive, error-prone operation), or even the elimination of process trip tests and their associated hardware altogether. Using both Shutdown System (SDS) 1 and SDS2, it is possible to obtain at least three, and more often six, independent, redundant measurements of each of many process variables. If signals from the reactor regulating, containment and emergency coolant injection (ECI) systems are also used, then it is possible to obtain up to 13 independent, redundant measurements of many process variables. Assuming these measurements are truly independent, and that there are no common mode errors, calibration accuracy can be verified by intercomparing the nominally identical readings. A CANDU Owners Group (COG) R and D project was set up to evaluate this monitoring concept. This project has progressed through several phases: (1) data acquisition, (2) data analysis and algorithm development, and (3) on-line calibration analysis and operational experience

  3. Evaluation of different cleaning agents used for cleaning ultra tiltration membranes fouled by surface water

    NARCIS (Netherlands)

    Zondervan, Edwin; Roffel, Brian

    2007-01-01

    This paper reviews the published literature on potential membrane fouling components, available cleaning agents and possible interactions between cleaning agents and fouling components. It also lists the cleaning models available in the literature, and evaluates the advantages and disadvantages of t

  4. Evaluation of fire probabilistic safety assessment for a PWR plant

    International Nuclear Information System (INIS)

    The internal fire analysis of the level 1 power operation probability safety assessment (PSA) for Maanshan (PWR) Nuclear Power Plant (MNPP) was updated. The fire analysis adopted a scenario-based PSA approach to systematically evaluate fire and smoke hazards and their associated risk impact to MNPP. The result shows that the core damage frequency (CDF) due to fire is about six times lower than the previous one analyzed by the Atomic Energy Council (AEC), Republic of China in 1987. The plant model was modified to reflect the impact of human events and recovery actions during fire. Many tabulated EXCEL spread-sheets were used for evaluation of the fire risk. The fire-induced CDF for MNPP is found to be 2.1 E-6 per year in this study. The relative results of the fire analysis will provide the bases for further risk-informed fire protection evaluation in the near future. (author)

  5. TRIGA mark-II,III reactor safety re-evaluation

    International Nuclear Information System (INIS)

    For two years of 1990 and 1991, the safety of TRIGA Mk-II and III reactor has been re-evaluated. For this, domestic rules on research reactors has been reviewed, and as it was judged that standards on research reactors in USA is applicable to our ones it was evaluated whether TRIGA Mk-II and III reactors satisfy these standards. The site parameters and the environmental impacts during normal operation and hypothetical accident conditions have been analysed, and those parts for reactor facility and structure have been rewritten to fit SAR standard format based on the review of old SAR and maintenance manuals reflecting changes after the construction. Based on this re-evaluation, SAR, Technical Specifications, Radiation Emergency Plan, Environment Report, various procedures,etc. will be amended by the reactor management project. (Author)

  6. Seismic evaluation of safety systems at the Savannah River reactors

    International Nuclear Information System (INIS)

    A thorough review of all safety related systems in commercial nuclear power plants was prompted by the accident at the Three Mile Island Nuclear Power Plant. As a consequence of this review, the Nuclear Regulatory Commission (NRC) focused its attention on the environmental and seismic qualification of the industry's electrical and mechanical equipment. In 1980, the NRC issued Unresolved Safety Issue (USI) A-46 to verify the seismic adequacy of the equipment required to safely shut down a plant and maintain a stable condition for 72 hours. After extensive research by the NRC, it became apparent that traditional analysis and testing methods would not be a feasible mechanism to address this USI A-46 issue. The costs associated with utilizing the standard analytical and testing qualification approaches were exorbitant and could not be justified. In addition, the only equipment available to be shake table tested which is similar to the item being qualified is typically the nuclear plant component itself. After 8 years of studies and data collection, the NRC issued its Generic Safety Evaluation Report approving an alternate seismic qualification approach based on the use of seismic experience data. This experience-based seismic assessment approach will be the basis for evaluating each of the 70 pre-1972 commercial nuclear power units in the US and for an undetermined number of nuclear plants located in foreign countries. This same cost-effective approach developed for the commercial nuclear power industry is currently being applied to the Savannah River Production Reactors to address similar seismic adequacy issues. This paper documents the results of the Savannah River Plant seismic evaluation program. This effort marks the first complete (non-trial) application of this state-of-the-art USI A-46 resolution methodology

  7. Seismic evaluation of safety systems at the Savannah River reactors

    International Nuclear Information System (INIS)

    A thorough review of all safety related systems in commercial nuclear power plants was prompted by the accident at the Three Mile Island Nuclear Power Plant. As a consequence of this review, the Nuclear Regulatory Commission (NRC) focused its attention on the environmental and seismic qualification of the industry's electrical and mechanical equipment. In 1980, the NRC issued Unresolved Safety Issue (USI) A-46 to verify the seismic adequacy of the equipment required to safely shut down a plant and maintain a stable condition for 72 hours. After extensive research by the NRC, it became apparent that traditional analysis and testing methods would not be a feasible mechanism to address this USI A-46 issue. The costs associated with utilizing the standard analytical and testing qualification approaches were exorbitant and could not be justified. In addition, the only equipment available to be shake table testing which is similar to the item being qualified is typically the nuclear plant component itself. After 8 years of studies and data collection, the NRC issued its ''Generic Safety Evaluation Report'' approving an alternate seismic qualification approach based on the use of seismic experience data. This experience-based seismic assessment approach will be the basis for evaluating each of the 70 pre-1972 commercial nuclear power units in the United States and for an undetermined number of nuclear plants located in foreign countries. This same cost-effective developed for the commercial nuclear power industry is currently being applied to the Savannah River Production Reactors to address similar seismic adequacy issues. This paper documents the results of the Savannah River Plant seismic evaluating program. This effort marks the first complete (non-trial) application of this state-of-the-art USI A-46 resolution methodology

  8. Reversal of rocuronium-induced neuromuscular block by the selective relaxant binding agent sugammadex: a dose-finding and safety study

    DEFF Research Database (Denmark)

    Sorgenfrei, Iben F; Norrild, Kathrine; Larsen, Per Bo;

    2006-01-01

    Sugammadex (Org 25969) forms a complex with steroidal neuromuscular blocking agents, thereby reversing neuromuscular block. This study investigated the dose-response relation, safety, and pharmacokinetics of sugammadex to reverse rocuronium-induced block.......Sugammadex (Org 25969) forms a complex with steroidal neuromuscular blocking agents, thereby reversing neuromuscular block. This study investigated the dose-response relation, safety, and pharmacokinetics of sugammadex to reverse rocuronium-induced block....

  9. Criticality safety evaluation for dry vacuum system components

    International Nuclear Information System (INIS)

    A dry vacuum system is used at the Oak Ridge Y-12 Plant to collect dust that may include highly enriched (93.5% weight percent 235U) uranium oxides. Because it contains unfavorable geometry filtering components, criticality safety for the system depends upon controls on mass and moderation. This evaluation assumed that both of these controls were lost. The components which were studied were two bag filter separators and associated filter housings, and two sizes of cyclone separators. KENO-IV generalized geometry and sixteen group Hansen-Roach cross sections were used to model the system

  10. Systematic safety evaluation and life extension program in NPPs

    International Nuclear Information System (INIS)

    The Systematic Evaluation Programs (SEP) carried out in 80's on first-generation nuclear power plants in Spain consist in analyzing the compliance of the older plants with the safety requirements for the new ones. The most affected areas were: environmental qualification of electrical and I and C equipment; ECCS improvements; auxiliary system improvements; electrical systems; reactor protection systems; fire protection. The SEPs were followed by complementary programs on Management of Remaining Plant Life, aiming at making the facilities and SEP investments profitable. The experience gained in the SEP is important for collecting additional information for the Remaining Life Management and should be integrated with the Plant Life Extension Program (PLEX)

  11. Guidelines for retrospective safety analysis. Prepared for DRIVE II Project V2002 Horizontal Project for the Evaluation of Safety HOPES.

    OpenAIRE

    Oppe, S.

    1994-01-01

    This report contains the following contributions: Concepts and definitions (Oppe, S); Traffic in its social context (Chaloupka, C and Risser, R); The checklist as a retrospective safety tool (Chaloupka, C and Risser, R); Experimental design (Kulmala, R); Evaluation of the traffic process and its safety effects (Oppe, S); Methods for process evaluation (Steyvers, FJJM); Methods for product evaluation (Oppe, S); Accident analysis (Oppe, S); Time related models (Oppe, S); Behavioural models (Ste...

  12. Evaluation of Health, Safety and Environment (HSE Culture

    Directory of Open Access Journals (Sweden)

    Iraj Mohammadfam

    2013-01-01

    Full Text Available Studies have determined that the application of technical safety measures is not adequate to protect human, economic and environmental assets in industries. Therefore, promoting Health, Safety and Environment (HSE culture, as an alternative approach, is of great importance. The aim of this study was to evaluate and manage HSE culture among employees of an industrial sector in Iran. This descriptive-analytic research was carried out during the years 2009 and 2010. The statistical population included ten subsidiaries of the industry. To gather the required data, an HSE culture questionnaire was developed. SPSS software was also applied to analyze the data gathered. Data analysis determined that the mean of HSE culture scores was 262.7. Considering the borderline between the negative and positive HSE culture (279, it is inferred that 79.4% of personnel culture scores was negative. Finally, the study concluded that to improve safety culture in an organization, not only psychological and personal factors but also organizational and environmental factors should thoroughly be investigated. In this way, the actual problems would be identified, appropriate problem-solving methodologies be implemented and, ultimately incidents rate be reduced.

  13. Evaluation of Spinacia oleracea L. leaves mucilage as an innovative suspending agent

    OpenAIRE

    Amit Kumar Nayak; Dilipkumar Pal; Dipti Ranjan Pany; Biswaranjan Mohanty

    2010-01-01

    The present study was undertaken to evaluate the mucilage isolated from Spinacia oleracea L. leaves, commonly named spinach (family: Amaranthaceae) as an innovative suspending agent. Zinc oxide suspensions (20% w/v) were prepared using the mucilage of S. oleracea L. leaves as a suspending agent, and it was evaluated for its stability by using parameters like, sedimentation profile, degree of flocculation, and redispersibility. The effect of the tested mucilage on the suspension was compared w...

  14. Evaluation of antibacterial effects of pulp capping agents with direct contact test method

    OpenAIRE

    Yalcin, Muhammet; Arslan, Ugur; Dundar, Ayse

    2014-01-01

    Objectives: Calcium hydroxide has been used in dentistry as a major capping material having the capacity to introduce the formation of a mineralized dentin bridge, but it has no direct inducing effect to the pulp cells. The purpose of this study was to evaluate the antibacterial properties of three different pulp capping agents using a direct contact test (DCT). Materials and Methods: The antibacterial properties of three pulp capping agents were evaluated a DCT. For the DCT, wells (n = 12) o...

  15. Evaluation of propofol as a general anesthetic agent for minor oral surgical procedure.

    Science.gov (United States)

    Jaggi, Nitin; Kalra, Amit; Baghla, Gunpreet Kaur; Medsinge, Sonali V; Purohit, Nikhil

    2013-01-01

    Nausea and vomiting following anesthesia is a distressing problem for the patient as it increases the recovery time, intensity of nursing care and delays discharge. The aim of randomized controlled single blind study is to evaluate the efficacy and safety of subhypnotic doses of propofol for the prevention of postoperative nausea and vomiting (PONV) in day care management of cases in oral and maxillofacial surgeries. Twenty-five patient of ASA-1 with age ranging from 12 to 40 years were scheduled for various maxillofacial surgical cases like fracture, cyst enucleation, surgical removal of 3rd molar, etc. were given propofol at the dose of 2 to 2.5 mg/kg as induction dose and sedation was maintained with the dose 5 to 10 mg/min. There was no significant effect on heart rate, systolic and diastolic blood pressure, respiratory rate and oxygen saturation intraoperatively. In conclusion, a subhypnotic dose of propofol is fast acting, safe and easily controllable, short acting general anesthetic agent with rapid recovery. The study found that the PONV was significantly reduced in the patient with propofol, no hemodynamic derangements were noted in the postoperative period. PMID:24309336

  16. Synthesis and Biological Evaluation of Liguzinediol Mono- and Dual Ester Prodrugs as Promising Inotropic Agents

    Directory of Open Access Journals (Sweden)

    Jing Zhang

    2014-11-01

    Full Text Available The potent positive inotropic effect, together with the relatively low safety risk of liguzinediol (LZDO, relative to currently available inotropic drugs, has prompted us to intensively research and develop LZDO as a potent positive inotropic agent. In this study, to obtain LZDO alternatives for oral chronic administration, a series of long-chain fatty carboxylic mono- and dual-esters of LZDO were synthesized, and preliminarily evaluated for physicochemical properties and bioconversion. Enhanced lipophilic properties and decreased solubility of the prodrugs were observed as the side chain length increased. All esters showed conspicuous chemical stability in phosphate buffer (pH 7.4. Moreover, the enzymatic hydrolysis of esters in human plasma and human liver microsomes confirmed that the majority of esters were converted to LZDO, with release profiles that varied due to the size and structure of the side chain. In vivo pharmacokinetic studies following oral administration of monopivaloyl (M5, monodecyl (M10 and monododecyl (M12 esters demonstrated the evidently extended half-lives relative to LZDO dosed alone. In particular the monopivaloyl ester M5 exhibited an optimal pharmacokinetic profile with appropriate physiochemical characteristics.

  17. Corporate Functional Management Evaluation of the LLNL Radiation Safety Organization

    Energy Technology Data Exchange (ETDEWEB)

    Sygitowicz, L S

    2008-03-20

    A Corporate Assess, Improve, and Modernize review was conducted at Lawrence Livermore National Laboratory (LLNL) to evaluate the LLNL Radiation Safety Program and recommend actions to address the conditions identified in the Internal Assessment conducted July 23-25, 2007. This review confirms the findings of the Internal Assessment of the Institutional Radiation Safety Program (RSP) including the noted deficiencies and vulnerabilities to be valid. The actions recommended are a result of interviews with about 35 individuals representing senior management through the technician level. The deficiencies identified in the LLNL Internal Assessment of the Institutional Radiation Safety Program were discussed with Radiation Safety personnel team leads, customers of Radiation Safety Program, DOE Livermore site office, and senior ES&H management. There are significant issues with the RSP. LLNL RSP is not an integrated, cohesive, consistently implemented program with a single authority that has the clear roll and responsibility and authority to assure radiological operations at LLNL are conducted in a safe and compliant manner. There is no institutional commitment to address the deficiencies that are identified in the internal assessment. Some of these deficiencies have been previously identified and corrective actions have not been taken or are ineffective in addressing the issues. Serious funding and staffing issues have prevented addressing previously identified issues in the Radiation Calibration Laboratory, Internal Dosimetry, Bioassay Laboratory, and the Whole Body Counter. There is a lack of technical basis documentation for the Radiation Calibration Laboratory and an inadequate QA plan that does not specify standards of work. The Radiation Safety Program lack rigor and consistency across all supported programs. The implementation of DOE Standard 1098-99 Radiological Control can be used as a tool to establish this consistency across LLNL. The establishment of a site

  18. Efficacy, Safety, and Biomarkers of Single-Agent Bevacizumab Therapy in Patients with Advanced Hepatocellular Carcinoma

    OpenAIRE

    Boige, Valérie; Malka, David; Bourredjem, Abderrahmane; Dromain, Clarisse; Baey, Charlotte; Jacques, Nathalie; Pignon, Jean-Pierre; Vimond, Nadege; Bouvet-Forteau, Nathalie; De Baere, Thierry; Ducreux, Michel; Farace, Françoise

    2012-01-01

    The safety, efficacy, and potential biomarkers of activity of bevacizumab in patients with advanced hepatocellular carcinoma were assessed. Bevacizumab was active and well tolerated. The clinical value of circulating endothelial cells and interleukin-6 and -8 warrants further investigation.

  19. Naphthoflavones as Antiproliferative Agents: Design, Synthesis and Biological Evaluation.

    Science.gov (United States)

    Kumar, Dinesh; Singh, Onkar; Nepali, Kunal; Bedi, Pms; Qayum, Arem; Singh, Shashank; Jain, Subheet K

    2016-01-01

    The present study involves the design and synthesis of naphthoflavones as antiproliferative agents. The strategy presents naphthoflavones as hybrids of naphthyl based chalcones and flavones. A panel of human cancer cell lines were employed for the cytotoxicity studies. DK-13 exhibited significant cytoxicity against MiaPaCa-2 cell lines with IC50 value of 1.93 μM and 5.63 μM against MCF-7 cell lines. The compound DK-13 was found to induce apoptosis evidenced through phase contrast microscopy, DAPI staining, and mitochondrial membrane potential loss. The cell phase distribution studies indicated an increase from 11.26 % (control sample) to 55.19 % (sample treated with 20 μM compound DK-13) in the apoptotic population. PMID:26845133

  20. Review on the Evaluation System of Public Safety Carrying Capacity about Small Town Community

    Institute of Scientific and Technical Information of China (English)

    Ming; SUN; Tianyu; ZHU

    2014-01-01

    Recently,small town community public safety problem has been increasingly highlighted,but its research is short on public safety carrying capacity. Through the investigation and study of community public safety carrying capacity,this paper analyzes the problem of community public safety in our country,to construct index evaluation system of public safety carrying capacity in small town community. DEA method is used to evaluate public safety carrying capacity in small town community,to provide scientific basis for the design of support and standardization theory about small town community in public safety planning.

  1. Application of fuzzy integrated evaluation in the safety of coal industry of China

    Institute of Scientific and Technical Information of China (English)

    LIU Wei; TAO Shu-ren

    2005-01-01

    Based on fuzzy integrated evaluation theory, the safety of coal industry was analyzed, the factors affecting the safety of coal industry was considered, and its fuzzy integrated estimating theory and results were given. Finally this paper proposed a new method of industry safety estimation. According to this method, we can integrate the factors affecting coal industry and deal with the parameters and targets of evaluating factors by quantitative analysis, thus give a scientific and reasonable safety degree analyzing evaluation.

  2. Guidelines for evaluation of non-Safety Class 1 structural components having effects on Safety Class 1 equipment

    International Nuclear Information System (INIS)

    Non-Safety Class 1 piping, vessels, and equipment require substantial seismic evaluation to ensure that failure during an earthquake does not result in Safety Class 1 equipment pressure boundary failure, distortion, or loss of function. Design analysis guidelines for non-Safety Class 1 equipment are presented that address applied loads, seismic inertia loads, and damping values. Approaches to evaluating existing equipment anchorage, anchor bolt allowables, piping contributory masses for support evaluation, and proposed allowable stresses are discussed in this paper. Proposed allowables are developed for piping, electrical conduit, and heating and ventilation ducting. Applications of the guidelines to nuclear reactor and nuclear facilities are discussed

  3. The Safety of Erythropoiesis-Stimulating Agents for the Treatment of Anemia Resulting from Chronic Kidney Disease.

    Science.gov (United States)

    Robles, Nicolas Roberto

    2016-06-01

    Chronic kidney disease (CKD) anemia treatment was revolutionized in the late 1980s with the introduction of recombinant human erythropoietin. This and related erythropoiesis-stimulating agents (ESAs) greatly benefited patients by decreasing debilitating symptoms, improving their quality of life, and freeing them from dependence on blood transfusions with their associated complications such as infections, sensitization impeding transplantation, and secondary iron overload. However, even in the initial studies, untoward effects were noted in patients receiving ESAs, including worsening hypertension, seizures, and dialysis access clotting. Later, increased mortality, malignancy progression and even stroke were reported in renal patients. This review focuses on the safety issues of ESAs in CKD patients. PMID:26894799

  4. Environmental impact evaluation using an agent based simulation framework

    OpenAIRE

    Schroijen, M.J.T.; Van Tooren, M.J.L.

    2010-01-01

    Environmental issues play an increasingly important role in aviation, affecting the desirability of novel technologies directly. The desirability of a certain technology with respect to environmental issues is determined by the system of systems level impact instead of the often used system level impact. Changing this perspective introduces additional complexities in how the system level evaluation should be related to the desired system of systems (SoS) level evaluation. A framework is propo...

  5. Criticality Safety Evaluation Report for the Multi-Canister Overpack

    International Nuclear Information System (INIS)

    This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially built baskets containing a maximum of either 54 Mark IV or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operation at the Cold Vacuum Drying Facility,a nd storage in the Canister Storage Building. Many conservatisms have been built into this analysis, the primary one being the selection of the Keff = 0.95 criticality safety limit. This revision incorporates the analyses for the sampling/weld station in the Canister Storage Building and additional analysis of the MCO during the draining at CVDF. Additional discussion of the scrap basket model was added to show why the addition of copper divider plates was not included in the models

  6. Criticality safety evaluation report for the multi-canister overpack

    International Nuclear Information System (INIS)

    This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially built baskets containing a maximum of either 54 Mark 1V or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operations at the Cold Vacuum Drying Facility, and storage in the Canister Storage Building. Many conservatisms have been built into this analysis, the primary one being the selection of the keff = 0.95 criticality safety limit. Additional analyses in this revision include partial fuel basket loadings, loading 26.1 inch Mark IA fuel assemblies into Mark IV fuel baskets, and the revised fuel and scrap basket designs. The MCO MCNP model was revised to include the shield plug assembly

  7. 10CFR50.59 safety evaluations: trends, actions and issues

    International Nuclear Information System (INIS)

    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 a result of this transition, Detroit Edison had procedures in place and conducted personnel training. Approval of all safety evaluations were required by the on-site review board. The on-site board was given a presentation by engineers of the total design change. The off-site board delegated detailed reviews of most safety evaluations to the independent safety evaluation group (ISEG). Unlike the on-site review board, the ISEG and off-site review group focused primarily on the safety evaluation itself. This paper addresses industry trends that were studied, Detroit Edison's recent actions, and industry issues related to 10CFR50.59 safety evaluations

  8. Onychomycosis: Clinical findings, etiological agents and evaluation of laboratory methods

    Directory of Open Access Journals (Sweden)

    Dubljanin Eleonora

    2014-01-01

    Full Text Available The aim of this study was to identify the etiological agents in patients with suspected onychomycosis, and to carry out comparative testing of individual or combinations of tests: direct microscopy with KOH and Blankophor (BP, culturing on Sabouraud’s dextrose agar (SDA, diluted Sabouraud’s dextrose agar (D-SDA and dermatophyte test medium (DTM. From 70 nail samples (65 toenails, 5 fingernails, 46 (60.5% had at least one of five positive tests. Isolation was possible in 41, while in 5 samples the presence of fungi was observed by KOH and/or BP. Dermatophytes were most frequently isolated (80.5% where Trichophyton rubrum was predominant. Candida spp. was isolated in 9.8%, Aspergillus spp. 4.9%, Alternaria spp. 2.4% and Fusarium spp. 2.4%. Application of BP as an individual test was the most sensitive method. The combination of BP with DTM or D-SDA provides the best sensitivity and allows the identification of fungi to the species/genus level.

  9. 29 CFR 1960.11 - Evaluation of occupational safety and health performance.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Evaluation of occupational safety and health performance. 1960.11 Section 1960.11 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH... AND HEALTH PROGRAMS AND RELATED MATTERS Administration § 1960.11 Evaluation of occupational safety...

  10. 29 CFR 1960.79 - Self-evaluations of occupational safety and health programs.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Self-evaluations of occupational safety and health programs. 1960.79 Section 1960.79 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH... AND HEALTH PROGRAMS AND RELATED MATTERS Evaluation of Federal Occupational Safety and Health...

  11. Safety analysis and evaluation of the next fusion device

    International Nuclear Information System (INIS)

    As a part of safety evaluation, a probabilistic risk assessment (PRA) has been attempted for the Next Fusion Device system. Among the various events related to safety, a number of representative events have been selected for assessment, from the events in normal operation state, repair and maintenance state and accidental state. In the first chapter, in order to conduct the probabilistic risk assessment of the whole Fusion Experimental Reactor (FER), the data base required for the analysis was investigated in 1.1, the results on the failure mode and effects analysis (FMEA), accident sequence, radioactive inventory leakage flow path, event tree analysis (ETA) and fault tree analysis (FTA) were summarized in 1.2 to 1.5, respectively. Based on these results, accident initiating events were evaluated in 1.6, and overall risk was assessed in 1.7 and the tasks for the future were summarized in 1.8. It is important to analyze and evaluate various events during normal operations, repair and maintenance and accidents. However, due to the large uncertainties in the modeling of phenomena or the data base, there are many events for which realistic analyses are difficult. Three such events were selected and studied in chapter two. In 2.1, the temperature rise in the reactor structure after the Loss-of-Coolant-Accident caused by the decay heat under various heat removal conditions were investigated. In 2.2, the radiation dose of personnel during repair and maintenance period caused by the release of activated dust were estimated. Lastly, in 2.3 tritium behavior in the stainless steel first wall and graphite armour were studied. (author)

  12. KHNP Safety Culture Framework based on Global Standard, and Lessons learned from Safety Culture Evaluation

    International Nuclear Information System (INIS)

    In order to eliminate the vague fears of the people about the nuclear power and operate continuously NPPs, a strong safety culture of NPPs should be demonstrated. Strong safety culture awareness of workers can overcome social distrust about NPPs. KHNP has been a variety efforts to improve and establish safety culture of NPPs. Safety culture framework applying global standards was set up and safety culture assessment has been carried out periodically to enhance safety culture of workers. In addition, KHNP developed various safety culture contents and they are being used in NPPs by workers. As a result of these efforts, safety culture awareness of workers is changed positively and the safety environment of NPPs is expected to be improved. KHNP makes an effort to solve areas for improvement derived from safety culture assessment. However, there are some areas to take a long time in completing the work. Therefore, these actions are necessary to be carried out consistently and continuously. KHNP also developed recently safety culture enhancement system based on web. All information related to safety culture in KHNP will be shared through this web system and this system will be used to safety culture assessment. In addition to, KHNP plans to develop safety culture indicators for monitoring the symptoms of safety culture weakening

  13. KHNP Safety Culture Framework based on Global Standard, and Lessons learned from Safety Culture Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Younggab; Hur, Nam Young; Jeong, Hyeon Jong [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    In order to eliminate the vague fears of the people about the nuclear power and operate continuously NPPs, a strong safety culture of NPPs should be demonstrated. Strong safety culture awareness of workers can overcome social distrust about NPPs. KHNP has been a variety efforts to improve and establish safety culture of NPPs. Safety culture framework applying global standards was set up and safety culture assessment has been carried out periodically to enhance safety culture of workers. In addition, KHNP developed various safety culture contents and they are being used in NPPs by workers. As a result of these efforts, safety culture awareness of workers is changed positively and the safety environment of NPPs is expected to be improved. KHNP makes an effort to solve areas for improvement derived from safety culture assessment. However, there are some areas to take a long time in completing the work. Therefore, these actions are necessary to be carried out consistently and continuously. KHNP also developed recently safety culture enhancement system based on web. All information related to safety culture in KHNP will be shared through this web system and this system will be used to safety culture assessment. In addition to, KHNP plans to develop safety culture indicators for monitoring the symptoms of safety culture weakening.

  14. Ships in an Artificial Force Field: A Multi-agent System for Nautical Traffic and Safety

    NARCIS (Netherlands)

    Xiao, F.

    2014-01-01

    The main objective of this research is developing a simulation tool that provides information of detailed ship behavior in a specific navigational environment, on both the ship traffic level and the individual ship level, for safety analysis, decision making, planning of ports and waterways, and des

  15. Evaluation of methods for assessing toxicity of oil spill treating agents

    Energy Technology Data Exchange (ETDEWEB)

    Lumley, T.C.; Hollebone, B.P. [Environment Canada, Ottawa, ON (Canada); Harrison, S. [SAIC Canada, Ottawa, ON (Canada)

    2007-07-01

    The first counter-measure considered during an oil spill is the mechanical removal of the spilled oil, but this rarely collects more than 20 per cent of the spilled oil. When mechanical means are insufficient, it is advisable to use spill treating agents (STAs). The potential impact of STAs on the environment is estimated by assessing their in-vitro toxicity to sensitive or sentinel organisms. The typical endpoint in animal exposure models is acute lethality LC{sub 50}, which is the concentration that will be fatal to 50 per cent of the test population. The range of STAs include dispersants; shoreline washing agents; de-emulsifiers or emulsion inhibitors; herding agents; recovery agents; solidifiers or gelling agents; biodegradation agents; and, sinking agents. However, a thorough understanding of the overall toxicity of the agent to the environment must be determined along with the net environmental benefit. The agents must undergo rigorous toxicity evaluations to meet the requirements of the New Substances Notification or Significant New Activity Notification sections of the Canadian Environmental Protection Act of 1999. Environment Canada's guidelines for the use and acceptability of dispersants also address toxicity issues. In particular, emphasis has been on evaluating toxicity by the 96-hour rainbow trout lethality test. This paper presented challenges to the current test protocols and recommended that Environment Canada's guidelines for the use of oil STAs should be modified to include a broader definition of toxicity. The toxicity of a dispersant should be less than the toxicity of the water soluble fraction of an oil slick. However, sublethal effects of dispersant exposure, such as endocrine disruption, organ toxicity, mutagenicity and geotoxicity must be better understood. It was argued that testing on one fish species in an enclosed system does not adequately address a diverse marine environment. It was recommended that testing procedures

  16. Evaluating the impact of climate change on dam safety

    International Nuclear Information System (INIS)

    This paper presents a newly developed flood frequency model which can be used to forecast potential future flood levels based on current climate trends. It can then be used to assess the long-term safety of an important asset. Information from a meteorological station in North Bay, Ontario confirms that there has been a statistically evident trend for warmer winters over the last 3 decades. The model was used to assess the impact of climate change on dam safety. Results suggest that if the current climate trend continues, there may be a significant increase in the magnitude of the inflow design flood (IDF) for dams located on small-to medium-sized watersheds. However, the magnitude of IDF for dams located on large watersheds would likely be reduced. The model can be used to quantify potential future risks both in the design of new dams and in the long-term planning for existing dams. It is noted that there could be an unquantified risk if there was a rapid change in the climate. In order to address this issue, methodologies must predict the direction of change, estimate the magnitude of the changes, and evaluate the reliability of the predictions based on an assessment of the existing data sets and the predicted future conditions. 27 refs., 5 figs

  17. Pharmacokinetics and preliminary safety evaluation of azithromycin in adult horses.

    Science.gov (United States)

    Leclere, M; Magdesian, K G; Cole, C A; Szabo, N J; Ruby, R E; Rhodes, D M; Edman, J; Vale, A; Wilson, W D; Tell, L A

    2012-12-01

    Azithromycin is widely used in foals but has not been studied in adult horses. The goals of this study were to determine the pharmacokinetic profile and to make a preliminary assessment of the safety of azithromycin in adult horses. Azithromycin was administered intravenously (5 mg/kg) and intragastrically (10 mg/kg) to six healthy mares in a crossover design. Serial plasma samples, blood neutrophils, and pulmonary macrophages were collected for the measurement of azithromycin concentrations. Azithromycin was also administered orally (10 mg/kg) once a day for 5 days to five healthy mares for preliminary evaluation of safety in adult horses. The bioavailability of azithromycin following intragastric administration was 45 ± 12%. Concentrations within peripheral neutrophils and bronchoalveolar macrophages were several fold higher than that of plasma. Mild decreases in appetite (n = 3) and alterations in fecal consistency (n = 3) were noted following repeated oral administration. The pharmacokinetic profiles of azithromycin in adult horses, especially the slow elimination rate and intraneutrophil and intrapulmonary macrophage accumulation, demonstrate that it is conducive to use in this age group. Because of the gastrointestinal alterations noted, further studies are warranted before azithromycin can be recommended for use in adult horses. PMID:22136612

  18. Design and Evaluation of Buccoadhesive Compacts of Selective Antihypertensive Agents

    Directory of Open Access Journals (Sweden)

    Shantha Kumar G.S

    2012-09-01

    Full Text Available The purpose of this research was to design, develop and evaluate BC’s of enalapeil maleate using Carbopol 934P, HPMC 4KM, HPMC 15KM, and HPMC 100KM in various ratios such as 1:0, 1:1 & 0:1 by direct compression method. Effect of polymer type, proportion and combination was studied on the drug release rate, release mechanism and bioadhesive strength of the prepared formulations. The mixed blend was evaluated for preformulation parameters. The BC’s were evaluated for physical parameters, surface pH, Swelling studies, bioadhesive strength, content uniformity study, in vitro dissolution studies, ex vivo permeation studies and stability studies. The physical parameters and content uniformity of BC’s were found within specified limits. Swelling index studies and surface pH study results were found in the range of 131.19 to 378.33% after 6 hours and 5.73 to 5.95 after 4 hours. FTIR studies showed no evidence on interactions between drug, polymers, and excipients. In vitro drug release & ex vivo permeation for the formulation F2 was found 90.92 % & 85.23% at the end of 8 hr. Drug release and mucoadhesive strength were found to depend upon polymer type, proportion and viscosity. The release mechanism of was found to be of anomalous non-Fickian type. The stability studies revealed that there is no decrease in the drug content of F2 for the period of 3 months. This may be concluded that the stable formulation could be developed by incorporating carbopol and HPMC 4KM in the ratio of 1:1 controlling the release of enalapril maleate from BC’s.

  19. Synthesis and evaluation of flavanones as anticancer agents

    Directory of Open Access Journals (Sweden)

    Y Murti

    2014-01-01

    Full Text Available A few flavanones were synthesised by cyclisation of corresponding 3-(heteroaryl-1(2-hydroxyphenyl prop-2-en-1-one with sodium acetate in alcohol-water and evaluated for activity. Synthesised compounds were assayed for their in vitro anticancer activity against three human cancer cell lines, mammary adenocarcinoma (MCF7, human colon adenocarcinoma (HT29 and human kidney adenocarcinoma (A498 using sulforhodamine B dye. Results indicated that most of the compounds exhibited significant in vitro anticancer potential. Among them, compound having furan ring showed most potent activity against all the tested cell lines.

  20. Evaluation of Spinacia oleracea L. leaves mucilage as an innovative suspending agent

    Directory of Open Access Journals (Sweden)

    Amit Kumar Nayak

    2010-01-01

    Full Text Available The present study was undertaken to evaluate the mucilage isolated from Spinacia oleracea L. leaves, commonly named spinach (family: Amaranthaceae as an innovative suspending agent. Zinc oxide suspensions (20% w/v were prepared using the mucilage of S. oleracea L. leaves as a suspending agent, and it was evaluated for its stability by using parameters like, sedimentation profile, degree of flocculation, and redispersibility. The effect of the tested mucilage on the suspension was compared with various commonly used suspending agents, such as, tragacanth, bentonite, and sodium carboxymethyl cellulose (NaCMC at concentrations of 0.5, 1.0, and 2.0% w/v. The results obtained indicated that the mucilage of S. oleracea L. leaves could be used as a suspending agent, and the performance was found to be superior to both tragacanth and bentonite.

  1. Evaluation of Spinacia oleracea L. leaves mucilage as an innovative suspending agent.

    Science.gov (United States)

    Nayak, Amit Kumar; Pal, Dilipkumar; Pany, Dipti Ranjan; Mohanty, Biswaranjan

    2010-07-01

    The present study was undertaken to evaluate the mucilage isolated from Spinacia oleracea L. leaves, commonly named spinach (family: Amaranthaceae) as an innovative suspending agent. Zinc oxide suspensions (20% w/v) were prepared using the mucilage of S. oleracea L. leaves as a suspending agent, and it was evaluated for its stability by using parameters like, sedimentation profile, degree of flocculation, and redispersibility. The effect of the tested mucilage on the suspension was compared with various commonly used suspending agents, such as, tragacanth, bentonite, and sodium carboxymethyl cellulose (NaCMC) at concentrations of 0.5, 1.0, and 2.0% w/v. The results obtained indicated that the mucilage of S. oleracea L. leaves could be used as a suspending agent, and the performance was found to be superior to both tragacanth and bentonite. PMID:22247868

  2. Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested

  3. Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sheaffer, M.K.; Keeton, S.C.

    1993-09-20

    This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested.

  4. Application of Mixed Group Decision Making to Safety Evaluation of Agricultural Products

    OpenAIRE

    Zhao, Xiao-hong

    2012-01-01

    In view of the gravity of issues concerning safety of agricultural products and urgency of resolving these issues, after analyzing the problems existing in safety of agricultural products, this article offers a method for evaluating safety of agricultural products on the basis of mixed group decision making. First of all, it introduces the factors influencing safety evaluation of agricultural products; subsequently, given that the judgment matrices offered by the group of experts contain both...

  5. Dynamic probability evaluation of safety levels of earth-rockfill dams using Bayesian approach

    OpenAIRE

    Zi-wu FAN; Shu-hai JIANG; Zhang, Ming

    2009-01-01

    In order to accurately predict and control the aging process of dams, new information should be collected continuously to renew the quantitative evaluation of dam safety levels. Owing to the complex structural characteristics of dams, it is quite difficult to predict the time-varying factors affecting their safety levels. It is not feasible to employ dynamic reliability indices to evaluate the actual safety levels of dams. Based on the relevant regulations for dam safety classification in Chi...

  6. Safety Evaluation of LILW Repository for Special Safety Analyses on Potential Location Vrbina in Krsko Municipality

    International Nuclear Information System (INIS)

    Special safety evaluation for low and intermediate level waste repository was prepared as part of the Special Safety Analyses prescribed by Slovenian Nuclear safety Administration according to the nuclear law. Safety assessment has been performed for three repository types at Vrbina in Krsko municipality, on the potential location, close to the NPP Krsko: for a surface vault - type repository, constructed on artificial embankment (variant E); for a near-surface silos - type repository (variant B); and for an underground repository (variant D). The safety assessment of the three repository types consists of the dose assessment for workers within repository through its operating and closing phase: for the normal evolution of events and for abnormal events, as well as for the post closure repository phase: for the normal evolution (or design) scenarios and for alternative scenarios. The assessment has been performed in accordance with the IAEA recommendations and Slovenian national regulatory Acts. With the first step, potential events have been identified and in accordance with the repository type characteristics, scenarios have been developed. These scenarios have further been analysed from the nuclear safety point of view: each of scenarios identified as important, either due to the high occurrence to be expected or due to the expected strong consequences, has been calculated and the resulting effective equivalent doses to a member of the critical group have been compared to the dose constraints. This way, 6 scenarios for normal events within the period of repository operating and closing phase have been treated and 12 scenarios for the abnormal events. For the post closure repository period, we have identified several design scenarios for each of the three repository types and a number of alternative scenarios: 7 for the surface repository, 3 for the silos and 4 for the underground type of repository. In accordance with the SADRWM and ISAM methodology, we have

  7. Lipopeptides as the Antifungal and Antibacterial Agents: Applications in Food Safety and Therapeutics

    OpenAIRE

    Khem Raj Meena; Kanwar, Shamsher S.

    2015-01-01

    A lot of crops are destroyed by the phytopathogens such as fungi, bacteria, and yeast leading to economic losses to the farmers. Members of the Bacillus genus are considered as the factories for the production of biologically active molecules that are potential inhibitors of growth of phytopathogens. Plant diseases constitute an emerging threat to global food security. Many of the currently available antimicrobial agents for agriculture are highly toxic and nonbiodegradable and thus cause ext...

  8. Lipopeptides as the antifungal and antibacterial agents: applications in food safety and therapeutics.

    Science.gov (United States)

    Meena, Khem Raj; Kanwar, Shamsher S

    2015-01-01

    A lot of crops are destroyed by the phytopathogens such as fungi, bacteria, and yeast leading to economic losses to the farmers. Members of the Bacillus genus are considered as the factories for the production of biologically active molecules that are potential inhibitors of growth of phytopathogens. Plant diseases constitute an emerging threat to global food security. Many of the currently available antimicrobial agents for agriculture are highly toxic and nonbiodegradable and thus cause extended environmental pollution. Moreover, an increasing number of phytopathogens have developed resistance to antimicrobial agents. The lipopeptides have been tried as potent versatile weapons to deal with a variety of phytopathogens. All the three families of Bacillus lipopeptides, namely, Surfactins, Iturins and Fengycins, have been explored for their antagonistic activities towards a wide range of phytopathogens including bacteria, fungi, and oomycetes. Iturin and Fengycin have antifungal activities, while Surfactin has broad range of potent antibacterial activities and this has also been used as larvicidal agent. Interestingly, lipopeptides being the molecules of biological origin are environmentally acceptable. PMID:25632392

  9. 4S safety characteristics and evaluation of emergency planning zone

    International Nuclear Information System (INIS)

    The current basis for EPZ (Emergency Planning Zone) sizing was reviewed and the importance of a modernized EPZ for 4S (Super-Safe, Small and Simple) was discussed. Criteria for an appropriately sized EPZ were suggested based on mitigation of a Class-9 event, which requires core melt, due to 4S's inherent safety aspects. The radiological consequences based on the Class-9 event without core melt (mod-Class-9) were evaluated. An EPZ radius of 200 m could be satisfied whose TEDE (Total Effective Dose Equivalent) is calculated to be less than the allowable dose limit of 10 mSv, if the leak rates of the reactor vessel and containment vessel are successfully kept below 10%/day and 1%/day, respectively. The 4S is designed to keep the cover gas leak rate less than 10%/day and the containment leak rate less than 1%/day for a severe accident. (author)

  10. Preliminary safety evaluation for the plutonium stabilization and packaging system

    International Nuclear Information System (INIS)

    This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS

  11. Preliminary safety evaluation for the plutonium stabilization and packaging system

    Energy Technology Data Exchange (ETDEWEB)

    Shapley, J.E., Fluor Daniel Hanford

    1997-03-14

    This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS.

  12. Evaluation and qualification of novel control techniques with safety requirements

    International Nuclear Information System (INIS)

    The paper discusses the questions related to the assessment and qualification of new I and C-systems. The tasks of nuclear power plant I and Cs as well as the efficiency of the new techniques are reflected. Problems with application of new I and Cs and the state of application in Germany and abroad are addressed. Starting from the essential differencies between conventional and new I and C-systems it is evaluated, if and in which way existing safety requirements can be met and to what extent new requirements need to be formulated. An overall concept has to be developed comprising the definition of graded requirement profiles for design and qualification. Associated qualification procedures and tools have to be adapted, developed and tuned upon each other. (orig./HP)

  13. Safety evaluation of chemically modified beta-lactoglobulin administered intravaginally.

    Science.gov (United States)

    Guo, Xuetao; Qiu, Lixia; Wang, Yonghong; Wang, Yue; Meng, Yuanguang; Zhu, Yun; Lu, Lu; Jiang, Shibo

    2016-06-01

    Currently, there is no specific antiviral therapy for treatment of HPV infection. Jiang and colleagues previously reported that anhydride-modified proteins have inhibitory activities against multiple viruses including HPV. Here, we evaluated the safety of 3-hydroxyphthalic anhydride-modified bovine beta-lactoglobulin, designated JB01, vaginally applied in women infected by high-risk HPV. After the vaginal application of JB01 in 38 women for 3 months, no serious adverse events were reported, and normalization of the vaginal micro-environment has been observed. It can be concluded that JB01-BD is safe for vaginal use in HPV-infected women, suggesting its potential application for the treatment of HPV infection. J. Med. Virol. 88:1098-1101, 2016. © 2015 Wiley Periodicals, Inc. PMID:26629967

  14. Evaluation of the persistence in the induction of Sister Chromatid Exchanges (SCE) by alkylating agents

    International Nuclear Information System (INIS)

    The persistence in the induction of sister chromatid exchanges (SCE) by the alkylating agents methyl and ethyl-methanesulfonates (MMS and EMS) was evaluated. For it, to groups of mice its were administered a dose of these agents and later its were analyzed the induced SCE's in two periods: early and late. Both agents caused high increments of SCE in the early period and small in the late one; however, the caused lately by EMS was significantly bigger. This late induction of SCE by EMS possibly is associated with an epigenetic change or with the presence of etiladucts in the phosphodiester bonds of the DNA. (Author)

  15. Clinical evaluation of cissus quadrangularis and moringa oleifera and osteoseal as osteogenic agents in mandibular fracture

    OpenAIRE

    Singh, Vibha; Singh, Narendra; Pal, U. S.; Dhasmana, Satish; Mohammad, Shadab; Singh, Nimisha

    2011-01-01

    Background: Ayurveda the ancient science of medicine describes various herb preparations that achieve the hastening of bone healing. Harjor showed clinical efficacy in the treatment of fractures. Objectives: The comparative evaluation of herbal agents as osteogenic agents in mandibular fractures. Study design: The patients were divided into four groups. Group 1: Osteoseal; Group 3: Harjor (Cissus quadrangularis); Group 2: Moringa (Moringa Oleifera); Group 4: Placebo. Result and Conclusion: Pa...

  16. Five years of simulator evaluation - a contribution to safety culture

    International Nuclear Information System (INIS)

    Simulator training has been an important component in education and advanced training at a high level of nuclear power plant personnel for more than 25 years. From the beginning of simulator training, checking on the objectives of learning and feedback have been part and parcel of the effort. In the course of the revision of the 1990 Directive on Expertise of Licensed Personnel in Nuclear Power Plants composed by the German Federal Ministry for the Environment (BMU), the type and organization of evaluations and the inclusion of qualified simulator trainers were expressed in even more concrete terms. Simulator evaluation serves the purpose of assessing, on the basis of the goals of practical exercises and courses established jointly with nuclear power plant operators, the performance and the behavior of individual participants so as to obtain information and guidance for further work. In addition, both simulator trainers, the Simulator Center, and the operators are to receive feedback with respect to the courses held and for checking against plans. First experience since the introduction of simulator evaluation has shown a basically positive assessment by all participants, i.e. attendees, operators, and the Simulator Center, expressing important aspects in support of training. As new simulators were commissioned in the mid-nineties, this met one of the major requests by course participants for a realistic model of their working environment. The experience accumulated also helps optimum training by means of simulators and thus ultimately also contributes to the safety culture in German nuclear technology. (orig.)

  17. Studies in laboratory animals to assess the safety of anti-inflammatory agents in acute porphyria.

    OpenAIRE

    McColl, K E; Thompson, G G; Moore, M R

    1987-01-01

    The safety of various anti-inflammatory drugs in acute porphyria was assessed by examining their effect on rat hepatic haem synthesis. Azapropazone, chloroquine, and gold increased delta-aminolaevulinic acid (ALA) synthase activity, indicating that they are liable to precipitate porphyric crises. Aspirin, ibuprofen, indomethacin, ketoprofen, flurbiprofen, phenylbutazone, naproxen, prednisolone, and penicillamine did not increase ALA synthase activity and should be safe in porphyria. Though th...

  18. Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety report

    International Nuclear Information System (INIS)

    The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration (RD and D) programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments that lie

  19. Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety

    International Nuclear Information System (INIS)

    The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments that lie outside the

  20. Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety

    Energy Technology Data Exchange (ETDEWEB)

    Neall, Fiona; Pastina, Barbara; Snellman, Margit; Smith, Paul; Gribi, P.; Johnson, Lawrence

    2008-12-15

    The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments

  1. The awareness of employees in safety culture through the improved nuclear safety culture evaluation method

    International Nuclear Information System (INIS)

    After the Chernobyl nuclear accident in 1986, nuclear safety culture terminology was at first introduced emphasizing the importance of employees' attitude and organizational safety. The concept of safety culture was spread by INSAG 4 published in 1991. From that time, IAEA had provided the service of ASCOT for the safety culture assessment. However, many people still are thinking that safety culture is abstract and is not clear. It is why the systematic and reliable assessment methodology was not developed. Assessing safety culture is to identify what is the basic assumption for any organization to accept unconsciously. Therefore, it is very difficult to reach a meaningful conclusion by a superficial investigation alone. KHNP had been doing the safety culture assessment which was based on ASCOT methodology every 2 years. And this result had contributed to improving safety culture. But this result could not represent the level of organization's safety culture due to the limitation of method. So, KHNP has improved the safety culture method by benchmarking the over sea assessment techniques in 2011. The effectiveness of this improved methodology was validated through a pilot assessment. In this paper, the level of employees' safety culture awareness was analyzed by the improved method and reviewed what is necessary for the completeness and objectivity of the nuclear safety culture assessment methodology

  2. Discovery and Evaluation of Thiazinoquinones as Anti-Protozoal Agents

    Directory of Open Access Journals (Sweden)

    Marcel Kaiser

    2013-09-01

    Full Text Available Pure compound screening has identified the dioxothiazino-quinoline-quinone ascidian metabolite ascidiathiazone A (2 to be a moderate growth inhibitor of Trypanosoma brucei rhodesiense (IC50 3.1 μM and Plasmodium falciparum (K1 dual drug resistant strain (IC50 3.3 μM while exhibiting low levels of cytotoxicity (L6, IC50 167 μM. A series of C-7 amide and Δ2(3 analogues were prepared that explored the influence of lipophilicity and oxidation state on observed anti-protozoal activity and selectivity. Little variation in anti-malarial potency was observed (IC50 0.62–6.5 μM, and no correlation was apparent between anti-malarial and anti-T. brucei activity. Phenethylamide 7e and Δ2(3-glycine analogue 8k exhibited similar anti-Pf activity to 2 but with slightly enhanced selectivity (SI 72 and 93, respectively, while Δ2(3-phenethylamide 8e (IC50 0.67 μM, SI 78 exhibited improved potency and selectivity towards T. brucei rhodesiense compared to the natural product hit. A second series of analogues were prepared that replaced the quinoline ring of 2 with benzofuran or benzothiophene moieties. While esters 10a/10b and 15 were once again found to exhibit cytotoxicity, carboxylic acid analogues exhibited potent anti-Pf activity (IC50 0.34–0.035 μM combined with excellent selectivity (SI 560–4000. In vivo evaluation of a furan carboxylic acid analogue against P. berghei was undertaken, demonstrating 85.7% and 47% reductions in parasitaemia with ip or oral dosing respectively.

  3. Evaluation of Seismic Safety for Existing Nuclear Installations. Safety Guide (Russian Edition)

    International Nuclear Information System (INIS)

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  4. Consumer and farmer safety evaluation of application of botanical pesticides in black pepper crop protection

    NARCIS (Netherlands)

    Hernandez-Moreno, J.; Soffers, A.E.M.F.; Wiratno,; Falke, H.E.; Rietjens, I.; Murk, A.J.

    2013-01-01

    This study presents a consumer and farmer safety evaluation on the use of four botanical pesticides in pepper berry crop protection. The pesticides evaluated include preparations from clove, tuba root, sweet flag and pyrethrum. Their safety evaluation was based on their active ingredients being euge

  5. PSA analysis focused on Mochovce safety measure evaluation from operational safety point of view

    International Nuclear Information System (INIS)

    Mochovce NPP consists of four reaktor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present units 1 and 2 are in operation. As these units represent the second generation of WWER reactor design, additional safety measures were implemented to enhance operational and nuclear safety according to the recommendations of international audits and operational experience from other simular units (such as Dukovany and Bohunice). These requirements result into a number of safety measures grouped according to their purpose to achieve recent international requirements on nuclear and operational safety. The paper presents the bases used for specification of safety measures including their grouping into comprehensive tasks covering different areas of safety goals as well as structural organization of project management including participating companies and work performance. Results are also given regarding the contribution of selected safety measures to reduction of total core damage frequency. (authors)

  6. Safety Evaluation of Cosmetic Ingredients Regarding Their Skin Sensitization Potential

    Directory of Open Access Journals (Sweden)

    Winfried Steiling

    2016-03-01

    Full Text Available Up to today, product safety evaluation in the EU is predominantly based on data/information on their individual ingredients. Consequently, the quality and reliability of individual ingredient data is of vital interest. In this context, the knowledge about skin sensitization potential is an explicit need for both hazard and risk assessment. Proper skin sensitization data of the individual chemicals is essential, especially when dermal contact is intended, like for cosmetics. In some cases, e.g., in the presence of irritating chemicals, the combination of individual ingredients may also need to be evaluated to cover possible mixture effects. Today, it seems unlikely or even impossible that skin sensitization in humans can be adequately described by a single test result or even by a simple combination of a few data points (in vivo or in vitro. It is becoming evident that a set of data (including human data and market data and knowledge about the ingredient’s specific sensitizing potency needs to be taken into account to enable a reliable assessment of skin sensitization. A more in-depth understanding on mechanistic details of the Adverse-Outcome-Pathway of skin sensitization could contribute key data for a robust conclusion on skin sensitization.

  7. DNA vaccination for rabies: Evaluation of preclinical safety and toxicology

    Directory of Open Access Journals (Sweden)

    Rajni Garg

    2014-01-01

    Full Text Available The worldwide incidence of rabies and high rates of therapy failure, despite availability of effective vaccines indicate the need for timely and improved prophylactic approaches. DNA vaccination based on optimized formulation of lysosome-targeted glycoprotein of the rabies virus provides potential platform for preventing and controlling rabies. As per the pre-clinical requirements, listed in guidelines of Schedule Y, FDA and that of The European Agency for evaluation of Medicinal Products; we evaluated the acute (single dose – 14 days using three dosing levels, that is, the therapeutic (1×, average (5× and high dose (10× intramuscular toxicity in the rodent model Swiss Albino mice. Furthermore, the chronic intramuscular toxicity (repeated dose – 43 days with another 14 days for satellite groups was investigated using broad dosing levels ranging from low (7×, mid (14× to high (28× in Wistar rats. A range of parameters including physical, physiological, clinical, immunological, hematological along with histopathology profiles of target organs was monitored to assess the impact of vaccination. There were no observational adverse effects despite high dose administration of the DNA vaccine formulation. Thus, this study indicates the safety of next generation of vaccines as well as highlights their potential application.

  8. Strengthening of the nuclear safety regulatory body. Field evaluation review

    International Nuclear Information System (INIS)

    As a result of a request from the Preparation Committee of the Nuclear Regulatory Authority (NRA) in 1992, and as recommended by the CEC/RAMG (Commission of European Communities/Regulatory Assistance Management Group) and the Agency mission in July 1993 to the Slovak Republic, the project SLR/9/005 was approved in 1993 as a model project for the period 1994-1996. Current budge is $401,340 and disbursements to date amount to $312,873. The project time schedule has been extended to 1997. The major conclusions of this evaluation are as follows: The project responded to an urgent national need, as well as to a statutory mandate of the Agency, and was adequately co-ordinated with other international assistance programmes to NRA. The project was designed as a structured programme of assistance by means of expert missions, scientific visits and a limited amount of equipment, acting upon several key areas of NRA regulatory responsibilities. Agency assistance was provided in a timely manner. A high concentration of expert missions was noticed at the initial stages of the project, which posed some managements problems. This was corrected to some extent in the course of implementation. Additionally, some overlapping of expert mission recommendations suggests that improvements are needed in the design of such missions. The exposure to international regulatory practice and expertise has resulted in substantial developments of NRA, both in organizational and operational terms. The project can claim to have contributed to NRA having gained governmental and international confidence. NRA's role in the safety assessment of Bohunice V1 reconstruction, as well as in Bohunice V2 safety review, Bohunice A1 decommissioning and in informing the public, also points at the success achieved by the project. The institutional and financial support of the Government contributed decisively to the project achievements. (author). Figs, tabs

  9. Development and initial psychometric examination of the Home Safety and Beautification Assessment in mothers referred to treatment by child welfare agents.

    Science.gov (United States)

    Donohue, Brad; Pitts, Michelle; Chow, Graig M; Benning, Stephen D; Soto-Nevarez, Arturo; Plant, Christopher P; Allen, Daniel N

    2016-05-01

    Unintentional injury is the leading cause of death among children, with approximately 45% of injuries occurring in and around the home. Rates of home injury are particularly high in the homes of caregivers who are referred for intervention services by child welfare agents. However, there are few validated methods of home safety assessment available. The Home Safety and Beautification Assessment (HSBA) was developed to assist intervention planning specific to home safety and appearance in a sample of 77 mothers who were referred to treatment by Child Welfare Services. Exploratory factor analysis of HSBA items indicated that safety and appearance factors emerged across rooms in the home, and internal consistencies were good. For each room, the sums of assessors' safety and appearance intervention priority item scores were correlated with the assessors' global safety and appearance ratings of the entire home, respectively. The participants' overall room attractiveness scores were correlated with the assessors' overall room appearance intervention priority scores, whereas the participants' ratings of overall room safety were not correlated with the assessors' overall room safety intervention priority scores. Participants' scores on the Abuse subscale of the Child Abuse Potential Inventory, personal income, and education level were not associated with the assessors' home safety and appearance intervention priority ratings, suggesting the HSBA is assessing constructs that are distinct from child abuse potential and socioeconomic status. The results support the HSBA in a sample referred to treatment by child welfare agents. (PsycINFO Database Record PMID:26322799

  10. PERFORMANCE EVALUATION FOR DAMPING CONTROLLERS OF POWER SYSTEMS BASED ON MULTI-AGENT MODELS

    Institute of Scientific and Technical Information of China (English)

    Ancheng XUE; Yiguang HONG

    2009-01-01

    This paper proposes a multi-layer multi-agent model for the performance evaluation of power systems, which is different from the existing multi-agent ones. To describe the impact of the structure of the networked power system, .the proposed model consists of three kinds of agents that form three layers: control agents such as the generators and associated controllers, information agents to exchange the information based on the wide area measurement system (WAMS) or transmit control signals to the power system stabilizers (PSSs), and network-node agents such as the generation nodes and load nodes connected with transmission lines. An optimal index is presented to evaluate the performance of damping controllers to the system's inter-area oscillation with respect to the information-layer topology.Then, the authors show that the inter-area information exchange is more powerful than the exchange within a given area to control the inter-area low frequency oscillation based on simulation analysis.

  11. Study of system safety evaluation on LTO of national project. Systematizing safety assessment of nuclear operating plants

    International Nuclear Information System (INIS)

    Since the Fukushima Dai-ichi accident, the importance of 'system safety' has been recognized. Particularly, on the system safety assessment of plants in operation, the various degradation aspects with transition of time has been emphasized. Accordingly, functional degradation will be the assessment target, and the changes in the safety codes and the concept of safety will be dealt with; where, the reliability assessment will be made on the consolidation of important functions under a system, not on individual components. The basic function of the system will be evaluated for each systems and subsystems on all of the plant. Reliability assessment for which damage risk of the three key factors - Shut-down capability, Core cooling capability and Boundary conditions - will be evaluated by applying the Defence -in- Depth concept. (author)

  12. Development and application of an integrated evaluation framework for preventive safety applications

    NARCIS (Netherlands)

    Scholliers, J.; Joshi, S.; Gemou, M.; Hendriks, F.; Ljung Aust, M.; Luoma, J.; Netto, M.; Engstrom, J.; Leanderson Olsson, S.; Kutzner, R.; Tango, F.; Amditis, A.J.; Blosseville, J.M.; Bekiaris, E.

    2011-01-01

    Preventive safety functions help drivers avoid or mitigate accidents. No quantitative methods have been available to evaluate the safety impact of these systems. This paper describes a framework for the assessment of preventive and active safety functions, which integrates procedures for technical p

  13. FOREST GUARD: A complete safety for Wildlife using Mobile Agents and Sensor Clouds in WSN

    Directory of Open Access Journals (Sweden)

    Sumit Kumar Tetarave

    2012-11-01

    Full Text Available With growing human population and search for new habitus and unsustainable use of natural resources, over exploitation of forests and wildlife is taking place world over. This is resulting in drastic decline in the number of essential flora and fauna. We propose a complete safe guard model named Forest Guard, for saving wildlife from human as well as their own collisions. This model will not guard them directly; rather it will help in collecting vital information about their real-time condition and will alert the institutional mechanisms to take corrective initiatives. The paper mentions this indirect support in the form of wireless sensor networks (WSN. In WSN, our proposed model uses mobile agents (MAs for handling huge area communication and injecting them for different guarding issues of different species of wildlife. A novel concept of Virtual Sensor Cloud (VSC is being discussed to trace different group of endangered wild animals such as Tigers, Lions, Elephants, etc.

  14. Food safety involving ingestion of foods and beverages prepared with phthalate-plasticizer-containing clouding agents.

    Science.gov (United States)

    Yen, Tzung-Hai; Lin-Tan, Dan-Tzu; Lin, Ja-Liang

    2011-11-01

    In May 2011, the illegal use of the phthalate plasticizer di(2-ethylhexyl) phthalate in clouding agents for use in foods and beverages was reported in Taiwan. This food scandal has caused shock and panic among the majority of Taiwanese people and has attracted international attention. Phthalate exposure is assessed by ambient monitoring or human biomonitoring. Ambient monitoring relies on measuring chemicals in environmental media, foodstuff and consumer products. Human biomonitoring determines body burden by measuring the chemicals, their metabolites or specific reaction products in human specimens. In mammalian development, the fetus is set to develop into a female. Because the female phenotype is the default, impairment of testosterone production or action before the late phase may lead to feminizing characteristics. Phthalates disrupt the development of androgen-dependent structures by inhibiting fetal testicular testosterone biosynthesis. The spectrum of effects obtained following perinatal exposure of male rats to phthalates has remarkable similarities with the human testicular dysgenesis syndrome. Epidemiological studies have suggested associations between phthalate exposure and shorter gestational age, shorter anogenital distance, shorter penis, incomplete testicular descent, sex hormone alteration, precocious puberty, pubertal gynecomastia, premature thelarche, rhinitis, eczema, asthma, low birth weight, attention deficit hyperactivity disorder, low intelligence quotient, thyroid hormone alteration, and hypospadias in infants and children. Furthermore, many studies have suggested associations between phthalate exposure and increased sperm DNA damage, decreased proportion of sperm with normal morphology, decreased sperm concentration, decreased sperm morphology, sex hormone alteration, decreased pulmonary function, endometriosis, uterine leiomyomas, breast cancer, obesity, hyperprolactinemia, and thyroid hormone alteration in adults. Finally, the number of

  15. Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

    International Nuclear Information System (INIS)

    Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

  16. Evaluation Model for Capability of Enterprise Agent Coalition Based on Information Fusion and Attribute Reduction

    Institute of Scientific and Technical Information of China (English)

    Dongjun Liu; Li Li; and Jiayang Wang

    2016-01-01

    For the issue of evaluation of capability of enterprise agent coalition, an evaluation model based on information fusion and entropy weighting method is presented. The attribute reduction method is utilized to reduce indicators of the capability according to the theory of rough set. The new indicator system can be determined. Attribute reduction can also reduce the workload and remove the redundant information, when there are too many indicators or the indicators have strong correlation. The research complexity can be reduced and the efficiency can be improved. Entropy weighting method is used to determine the weights of the remaining indicators, and the importance of indicators is analyzed. The information fusion model based on nearest neighbor method is developed and utilized to evaluate the capability of multiple agent coalitions, compared to cloud evaluation model and D-S evidence method. Simulation results are reasonable and with obvious distinction. Thus they verify the effectiveness and feasibility of the model. The information fusion model can provide more scientific, rational decision support for choosing the best agent coalition, and provide innovative steps for the evaluation process of capability of agent coalitions.

  17. Evaluation of new pH control agents for PWR secondary water systems. Final report

    International Nuclear Information System (INIS)

    This report presents an account of work evaluating new organic pH control agents for PWR station secondary systems. A discussion of corrosion control with pH controlling amines is given together with some information on current utility practice with volatile amines. The report describes opportunities for improved corrosion control with new pH controlling amines and the selection of candidates for laboratory evaluation. Progress on EPRI program RP 1571-7, ''Spectroscopic Characterization Methods for New pH Control Agents'', is presented. Also presented is an outline of the second phase of the RP 1571-7 program which was directed toward ''Evaluation of pH Control Agents in Simulated Steam Generator Tubesheet Crevice Environments.'' Quinuclidine and diaminopropane were evaluated using laser Raman spectroscopy. Hydrothermal stability and pH properties at temperature were determined. Quinuclidine was superior to diaminopropane and presents advantages over ammonia, hydrazine and morpholine for plant use as a pH control agent. It was further evaluated in tests with a scaled PWR crevice simulator for corrosion compatibility as well as pH control. 17 refs., 22 figs., 9 tabs

  18. Preliminary Criticality Safety Evaluation for In Situ Grouting in the Subsurface Disposal Area

    Energy Technology Data Exchange (ETDEWEB)

    Slate, L.J.; Taylor, J.T.

    2000-08-31

    A preliminary criticality safety evaluation is presented for in situ grouting in the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory. The grouting materials evaluated are cement and paraffin. The evaluation determines physical and administrative controls necessary to preclude criticality and identifies additional information required for a final criticality safety evaluation. The evaluation shows that there are no criticality concerns with cementitious grout but a neutron poison such as boron would be required for the use of the paraffin matrix.

  19. Preliminary Criticality Safety Evaluation for In Situ Grouting in the Subsurface Disposal Area

    Energy Technology Data Exchange (ETDEWEB)

    Slate, Lawrence J; Taylor, Joseph Todd

    2000-08-01

    A preliminary criticality safety evaluation is presented for in situ grouting in the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory. The grouting materials evaluated are cement and paraffin. The evaluation determines physical and administrative controls necessary to preclude criticality and identifies additional information required for a final criticality safety evaluation. The evaluation shows that there are no criticality concerns with cementitious grout but a neutron poison such as boron would be required for the use of the paraffin matrix.

  20. Preliminary Criticality Safety Evaluation for In Situ Grouting in the Subsurface Disposal Area

    International Nuclear Information System (INIS)

    A preliminary criticality safety evaluation is presented for in situ grouting in the Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory. The grouting materials evaluated are cement and paraffin. The evaluation determines physical and administrative controls necessary to preclude criticality and identifies additional information required for a final criticality safety evaluation. The evaluation shows that there are no criticality concerns with cementitious grout but a neutron poison such as boron would be required for the use of the paraffin matrix

  1. Development of the evaluation methods in reactor safety analyses and core characteristics

    International Nuclear Information System (INIS)

    In order to support the safety reviews by NRA on reactor safety design including the phenomena with multiple failures, the computer codes are developed and the safety evaluations with analyses are performed in the areas of thermal hydraulics and core characteristics evaluation. In the code preparation of safety analyses, the TRACE and RELAP5 code were prepared to conduct the safety analyses of LOCA and beyond design basis accidents with multiple failures. In the core physics code preparation, the functions of sensitivity and uncertainty analysis were incorporated in the lattice physics code CASMO-4. The verification of improved CASMO-4 /SIMULATE-3 was continued by using core physics data. (author)

  2. Multicenter analysis of tolerance and clinical safety of the extracellular MR contrast agent gadobenate dimeglumine (MultiHance registered)

    International Nuclear Information System (INIS)

    Purpose: Retrospective analysis of the occurrence of adverse events and the diagnostic efficacy of a paramagnetic contrast agent with weak intermittent protein binding and high relaxivity. Materials end methods: Postmarketing surveillance studies for gadobenate dimeglumine (MultiHance, BRACCO Altana Pharma, Constance) were conducted in Germany between 1998 and 2006 and then retrospectively analyzed. Demographic data, relevant comorbidities, and allergies were recorded. The safety and tolerability of MultiHance were logged on a standardized data sheet. Results: A total of 38568 patients were included in the study. 829 patients (2.1%) had a known intolerance against contrast media. The examined regions included the central nervous system, the liver, and the vascular bed. The injection rate with automated injectors (n = 10456) varied between 1.0 und 3.0 ml/sec in 86.5% of patients. Adverse events totaled 1.2%. 11 patients (0.03%) experienced serious adverse events. The most frequent findings were nausea, vomiting and a feeling of warmth. Conclusion: MultiHance is a safe and very well tolerated contrast agent for magnetic resonance imaging (MRI) with a profile and frequency of adverse events similar to other extracellular MR contrast materials. (orig.)

  3. FORMULATION AND EVALUATION OF TOPICAL DICLOFENAC SODIUM GEL USING DIFFERENT GELLING AGENT

    Directory of Open Access Journals (Sweden)

    Y. S. TANWAR, AMIT KUMAR JAIN

    2013-09-01

    Full Text Available The present research has been undertaken with the aim to develop a topical gel formulation of Diclofenac sodium usingdifferent gelling agent carbopol, Na CMC, HPMC (K4M and sodium alginate in different concentration, which wouldattenuate the gastrointestinal relater toxicities associated with oral administration. They were evaluated for physicochemicalproperties such as homogeneity, grittiness, viscosity, pH, Spreadability, drug content, skin irritancy, in vitro drug release,stability studies. The in vitro drug release rate of gel was evaluated using Franz diffusion cell containing cellophanemembrane with phosphate buffer pH 6.8 as the receptor medium. Studies showed that drug release was decrease withincrease in gelling agent concentration because polymer concentration increases, viscosity increases. Drug was absorbedfrom site of application as long as it remains in higher concentration gelling agent in solution form.Keywords: Diclofenac Sodium, carbopol, hydroxyl propyl methyl cellulose, sodium alginate anti‐inflammatory activity.

  4. Efficacy and Safety of Antifibrinolytic Agents in Reducing Perioperative Blood Loss and Transfusion Requirements in Scoliosis Surgery: A Systematic Review and Meta-Analysis

    OpenAIRE

    WANG, Meng; Zheng, Xin-Feng; Jiang, Lei-Sheng

    2015-01-01

    Background Routine use of antifibrinolytic agents in spine surgery is still an issue of debate. Objective To gather scientific evidence for the efficacy and safety of antifibrinolytic agents including aprotinin, tranexamic acid (TXA) and epsilon aminocaproic acid (EACA, traditionally known as Amicar) in reducing perioperative blood loss and transfusion requirements in scoliosis surgery. Methods We conducted a systematic review and meta-analysis for randomized controlled trials (RCTs), retrosp...

  5. Safety evaluation and management of complex systems: A system engineering approach

    OpenAIRE

    Guillerm, Romaric; Demmou, Hamid; Sadou, Nabil

    2012-01-01

    International audience This paper addresses the problem of safety evaluation of complex systems. It proposes an original and rigorous approach that integrates safety analysis in system engineering processes. The approach is based on system engineering (SE) principles and uses the famous industrial SE standard ANSI/EIA-632. The objective is to help designers and safety engineers in safety management of complex systems. For an efficient design, the model driven design is adopted through the ...

  6. Methodology development for statistical evaluation of reactor safety analyses

    International Nuclear Information System (INIS)

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

  7. Modelling operator cognitive interactions in nuclear power plant safety evaluation

    International Nuclear Information System (INIS)

    The overall objectives of the study were to review methods which are applicable to the analysis of control room operator cognitive interactions in nuclear plant safety evaluations and to indicate where future research effort in this area should be directed. This report is based on an exhaustive search and review of the literature on NPP (Nuclear Power Plant) operator error, human error, human cognitive function, and on human performance. A number of methods which have been proposed for the estimation of data for probabilistic risk analysis have been examined and have been found wanting. None addresses the problem of diagnosis error per se. Virtually all are concerned with the more easily detected and identified errors of action. None addresses underlying cause and mechanism. It is these mechanisms which must be understood if diagnosis errors and other cognitive errors are to be controlled and predicted. We have attempted to overcome the deficiencies of earlier work and have constructed a model/taxonomy, EXHUME, which we consider to be exhaustive. This construct has proved to be fruitful in organizing our thinking about the kinds of error that can occur and the nature of self-correcting mechanisms, and has guided our thinking in suggesting a research program which can provide the data needed for quantification of cognitive error rates and of the effects of mitigating efforts. In addition a preliminary outline of EMBED, a causal model of error, is given based on general behavioural research into perception, attention, memory, and decision making. 184 refs

  8. Criticality safety evaluation for dry vacuum system components

    International Nuclear Information System (INIS)

    A dry vacuum system is used at the Oak Ridge Y-12 Plant to collect dust that may include highly enriched (93.5 wt% 235U) uranium oxides. Because it contains unfavorable geometry filtering components, criticality safety for the system depends on controls on mass and moderation. This evaluation assumed that both of these controls were lost. The components that were studied were two bag filter separators and associated filter housings, and two sizes of cyclone separators. The KENO-IV generalized geometry and 16-group Hansen-Roach cross sections were used to model the system. Even if the mass and moderation controls on the dry vacuum system fail, it is very unlikely that a criticality accident would occur. The uranium mixture does not tend to mix well with water and so should reamin undermoderated. Critical conditions can only be achieved with well-moderated, high-uranium content, low-density mixtures. It is improbable that such a mixture could occur in this system

  9. Krypton-85 hydrofracture engineering feasibility and safety evaluation

    International Nuclear Information System (INIS)

    Engineering studies have been made to determine the hazards associated with the disposal of 85Kr using the hydrofracture process. To assess the hazards, an effort has been made to identify the equipment required to entrain and dissolve the noble gas into the grout stream at hydrofracture pressure (up to 350 bar). Off-the-shelf or slightly modified equipment has been identified for safe and effective compression and gas-grout mixing. Each monthly injection disposes of 1.6 x 106 Ci of 85Kr. By connecting only one gas cylinder to the injection system at a time, the maximum amount of krypton likely to be released as a result of equipment failure is limited to 128,000 Ci. An evaluation by Los Alamos Technical Associates shows that releasing this amount of gas in less than one hour under worst-case meteorological conditions through a 30-m stack would result in a whole-body dose of 170 millirem at a distance of 1 km from the facility. A krypton collection and recovery system can further reduce this dose to 17 millirem; increasing the distance to the site boundary to 3 km can also reduce the dose by a factor of ten. Lung and skin dose estimates are 1.6 and 120 times the whole-body dose, respectively. These are all worst-case values; releases under more typical conditions would result in a significantly lower dose. No insurmountable safety or engineering problems have been identified

  10. Krypton-85 hydrofracture engineering feasibility and safety evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Peretz, F.J.; Muller, M.E.; Pan, P.Y.

    1981-07-01

    Engineering studies have been made to determine the hazards associated with the disposal of /sup 85/Kr using the hydrofracture process. To assess the hazards, an effort has been made to identify the equipment required to entrain and dissolve the noble gas into the grout stream at hydrofracture pressure (up to 350 bar). Off-the-shelf or slightly modified equipment has been identified for safe and effective compression and gas-grout mixing. Each monthly injection disposes of 1.6 x 10/sup 6/ Ci of /sup 85/Kr. By connecting only one gas cylinder to the injection system at a time, the maximum amount of krypton likely to be released as a result of equipment failure is limited to 128,000 Ci. An evaluation by Los Alamos Technical Associates shows that releasing this amount of gas in less than one hour under worst-case meteorological conditions through a 30-m stack would result in a whole-body dose of 170 millirem at a distance of 1 km from the facility. A krypton collection and recovery system can further reduce this dose to 17 millirem; increasing the distance to the site boundary to 3 km can also reduce the dose by a factor of ten. Lung and skin dose estimates are 1.6 and 120 times the whole-body dose, respectively. These are all worst-case values; releases under more typical conditions would result in a significantly lower dose. No insurmountable safety or engineering problems have been identified.

  11. Studies on the Safety Evaluation of Radurized Indian Mackerel

    International Nuclear Information System (INIS)

    A 90-day feeding study with Wistar rats, including single reproduction study, has been carried out to evaluate the safety of radurized (150 krad) Indian mackerel. Three groups of animals were given stock rations, unirradiated mackerel diet or irradiated mackerel diet. Body weight gains for males and females fed the irradiated mackerel diet were comparable with the male and female rats given the unirradiated diet throughout the study. The group fed on stock rations showed relatively lower body weight gains. Food efficiency ratios were similar in rats fed irradiated and unirradiated mackerel diets. No intergroup differences were observed pertaining to the fertility of males or females that could be attributed to the ingestion of irradiated fish. The numbers of pups delivered and retained during lactation periods by females fed irradiated or unirradiated diets were similar. No significant differences pertaining to the haematological profiles were seen in animals belonging to different groups. Likewise, detailed clinical chemistry data and other biochemical investigations involving various serum and liver enzymes and other constituents failed to show any significant changes. Relative and absolute weights of various organs and gross pathological data also showed no significant differences between animals fed on unirradiated and irradiated mackerel diets. (author)

  12. Studies on the safety evaluation of radurized Indian mackerel

    International Nuclear Information System (INIS)

    A 90-day feeding study with Wistar rats, including single reproduction study, has been carried out to evaluate the safety of radurized (150 krad) Indian mackerel. Three groups of animals were given stock rations, unirradiated mackerel diet or irradiated mackerel diet. Body weight gains for males and females fed the irradiated mackerel diet were comparable with the male and female rats given the unirradiated diet throughout the study. The group fed on stock rations showed relatively lower body weight gains. Food efficiency ratios were similar in rats fed irradiated and unirradiated mackerel diets. No intergroup differences were observed pertaining to the fertility of males or females that could be attributed to the ingestion of irradiated fish. The numbers of pups delivered and retained during lactation periods by females fed irradiated or unirradiated diets were similar. No significant differences pertaining to the haematological profiles were seen in animals belonging to different groups. Likewise, detailed clinical chemistry data and other biochemical investigations involving various serum and liver enzymes and other constituents failed to show any significant changes. Relative and absolute weights of various organs and gross pathological data also showed no significant differences between animals fed on unirradiated and irradiated mackerel diets. (author)

  13. Synthesis and biological evaluation of andrographolide derivatives as potent anti-HIV agents

    Institute of Scientific and Technical Information of China (English)

    Bin Wang; Jing Li; Wen Long Huang; Hui Bin Zhang; Hai Qian; Yong Tang Zheng

    2011-01-01

    A series of Andro derivatives were described and evaluated for their anti-HIV activity in vitro. Compound 10 and 16b, of which TI were >10, had some anti-HTV-1 activity in vitro. Therein, compound 10 which was the best potent compound, could serve as a new lead for further development of anti-AIDS agents.

  14. Assessment of oral toxicity and safety of pentamethylchromanol (PMCol), a potential chemopreventative agent, in rats and dogs

    International Nuclear Information System (INIS)

    lower levels is considered to be less likely to result in toxicity following 28 days of exposure. Sex-related differences were seen in rats. Male rats appeared to have greater sensitivity to nephrotoxicity, while female animals had a greater incidence of hepatoxicity and changes in hematological parameters evaluated, especially at a dose of 500 mg/kg/day, which correlated to the higher plasma drug levels in female rats. It appeared that dogs were generally more sensitive than rats to oral administration of PMCol. Further examination of the potential toxic effects of PMCol in longer term studies is required prior to understanding the full risks of PMCol administration as a chemopreventative agent.

  15. Safety Evaluation Report related to the operation of Millstone Nuclear Power Station Unit No. 3 (Docket No. 50-4423). Supplement No. 1

    International Nuclear Information System (INIS)

    In July 1984 staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report regarding the application of Northeast Nuclear Energy Company (applicant and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The facility is located in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. This first supplement to NUREG-1031 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

  16. Safety Evaluation Report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). Supplement No. 1

    International Nuclear Information System (INIS)

    In April 1986 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. This first supplement to NUREG-0781 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

  17. A high performance core for OSI management agents: implementation, simulation and performance evaluation

    OpenAIRE

    Rivalino, Matias Júnior

    1999-01-01

    This article presents a proposal of a multithreaded core for an OSI/ISO management agents including its modeling, simulation and performance evaluation. The proposed model i s compared against another one (unthreaded core) which is the commonly adopted model by the most of the network management systems. All the modeling and simulation process were done at the a gent core level. Therefore the performance evaluation do not consider any effect of the communication layers, dealing with the perfo...

  18. Efficacy and safety of biological agents for systemic juvenile idiopathic arthritis

    DEFF Research Database (Denmark)

    Tarp, Simon; Amarilyo, Gil; Foeldvari, Ivan;

    2016-01-01

    assessed by applying the Grading of Recommendations Assessment, Development, and Evaluation (GRADE) methodology. RESULTS: From the 493 citations originally identified, 5 RCTs were eligible for inclusion-one each for anakinra, canakinumab and tocilizumab and two for rilonacept: all vs placebo. While all...

  19. Achieving excellence in 10CFR50.59 safety evaluation programs

    International Nuclear Information System (INIS)

    This paper addresses approaches to upgrading 10CFR50.59 safety evaluation programs. Specific advantages to different approaches and industry trends are identified based on surveys of industry practices conducted by the author and the author's experience in reviewing and upgrading safety evaluation programs. Topics discussed include: identification of need and assignment of responsibility; establishment of policy, including screening proposed changes for applicability, definitions of increased probability, increased consequences, and reduced margin of safety, and responsibility assignment for writing and reviewing safety evaluations; personnel training; and program implementation and monitoring

  20. Recent advances in evaluation of oxime efficacy in nerve agent poisoning by in vitro analysis

    International Nuclear Information System (INIS)

    The availability of highly toxic organophosphorus (OP) warfare agents (nerve agents) underlines the necessity for an effective medical treatment. Acute OP toxicity is primarily caused by inhibition of acetylcholinesterase (AChE). Reactivators (oximes) of inhibited AChE are a mainstay of treatment, however, the commercially available compounds, obidoxime and pralidoxime, are considered to be rather ineffective against various nerve agents, e.g. soman and cyclosarin. This led to the synthesis and investigation of numerous oximes in the past decades. Reactivation of OP-inhibited AChE is considered to be the most important reaction of oximes. Clinical data from studies with pesticide-poisoned patients support the assumption that the various reactions between AChE, OP and oxime, i.e. inhibition, reactivation and aging, can be investigated in vitro with human AChE. In contrast to animal experiments such in vitro studies with human tissue enable the evaluation of oxime efficacy without being affected by species differences. In the past few years numerous in vitro studies were performed by different groups with a large number of oximes and methods were developed for extrapolating in vitro data to different scenarios of human nerve agent poisoning. The present status in the evaluation of new oximes as antidotes against nerve agent poisoning will be discussed

  1. Dynamic probability evaluation of safety levels of earth-rockfill dams using Bayesian approach

    Institute of Scientific and Technical Information of China (English)

    Zi-wu FAN; Shu-hai JIANG; Ming ZHANG

    2009-01-01

    In order to accurately predict and control the aging process of dams, new information should be collected continuously to renew the quantitative evaluation of dam safety levels. Owing to the complex structural characteristics of dams, it is quite difficult to predict the time-varying factors affecting their safety levels. It is not feasible to employ dynamic reliability indices to evaluate the actual safety levels of dams. Based on the relevant regulations for dam safety classification in China, a dynamic probability description of dam safety levels was developed. Using the Bayesian approach and effective information mining, as well as real-time information, this study achieved more rational evaluation and prediction of dam safety levels. With the Bayesian expression of discrete stochastic variables, the a priori probabilities of the dam safety levels determined by experts were combined with the likelihood probability of the real-time check information, and the probability information for the evaluation of dam safety levels was renewed. The probability index was then applied to dam rehabilitation decision-making. This method helps reduce the difficulty and uncertainty of the evaluation of dam safety levels and complies with the current safe decision-making regulations for dams in China. It also enhances the application of current risk analysis methods for dam safety levels.

  2. Safety re-evaluation of the HOR reactor

    International Nuclear Information System (INIS)

    State. Requirement C16 in the new licence asks for a periodical integral safety re-evaluation of the HOR reactor every 10 years and starting after 2 years

  3. Comprehensive evaluation of new probabilistic safety analyses (PSA) for nuclear power stations outside Germany and status report on safety engineering

    International Nuclear Information System (INIS)

    This report was prepared on behalf of the Minister of Environment, Nature Conservation and Nuclear Safety. It summarizes the results of an analysis of the state of the art of foreign Probabilistic Safety Assessments (PSA) for nuclear power plants. Main features of selected PSA documents, characterizing methods and their application within the framework of operational safety assessment, are presented as well as insights gained from discussions with utilities and an authority. German examples of PSA were compared to the foreign analyses using experiences of the TUeV Nord e.V. from reviewing PSA. This comparison covers PSA of level 1. It was found that German PSA methods are generally comparable to the foreign approaches. Nevertheless differences were found with respect to the scope of operational states covered by the analyses, the details down to which human error analyses were performed as well as some special issues. The foreign examples demonstrate an extended application of PSA within the operational safety management. Experiences that were gained within this process over years form an appropriate basis for the establishment of probabilistic safety criteria as well as procedures for incorporating PSA into the operational safety evaluation process. A procedure is proposed for further performing and evaluating PSA and their results in Germany. (orig.)

  4. Safety evaluation report. Fast Flux Test Facility. Project No. 448

    International Nuclear Information System (INIS)

    Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance

  5. Safety evaluation report. Fast Flux Test Facility. Project No. 448

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-01

    Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance.

  6. Safety culture evaluation and asset root cause analysis

    International Nuclear Information System (INIS)

    This paper examines the role of organizational and management factors in nuclear power plant safety through the use of operating experiences. The ASSET (Assessment of Safety Significant Events Team) reports of thirteen plants (total thirty events) have been analyzed in term of twenty organizational dimensions (factors) identified by Brookhaven National Laboratory and Pennsylvania State University. For three plants detailed results are reported in this paper. The results of thirteen plants are summarized in the form of a table. The study tends to confirm that organizational and management factors play an important role in plant safety. The twenty organizational dimensions and their definitions, in general, were adequate in this study. Formalization, Safety Culture, Technical Knowledge, Training, Roles-Responsibilities and Problem Identification appear to be key organizational factors which influence the safety of nuclear power plants studied

  7. Efficacy, Safety, and Biomarkers of Single-Agent Bevacizumab Therapy in Patients with Advanced Hepatocellular Carcinoma

    Science.gov (United States)

    Malka, David; Bourredjem, Abderrahmane; Dromain, Clarisse; Baey, Charlotte; Jacques, Nathalie; Pignon, Jean-Pierre; Vimond, Nadege; Bouvet-Forteau, Nathalie; De Baere, Thierry; Ducreux, Michel; Farace, Françoise

    2012-01-01

    Objective. Hepatocellular carcinoma (HCC) is a highly vascularized tumor in which neoangiogenesis contributes to growth and metastasis. We assessed the safety, efficacy, and potential biomarkers of activity of bevacizumab in patients with advanced HCC. Methods. In this phase II trial, eligible patients received bevacizumab, 5 mg/kg or 10 mg/kg every 2 weeks. The disease-control rate at 16 weeks (16W-DCR) was the primary endpoint. Circulating endothelial cells (CECs) and plasma cytokines and angiogenic factors (CAFs) were measured at baseline and throughout treatment. Results. The 16W-DCR was 42% (95% confidence interval, 27%–57%). Six of the 43 patients who received bevacizumab achieved a partial response (objective response rate [ORR], 14%). Grade 3–4 asthenia, hemorrhage, and aminotransferase elevation occurred in five (12%), three (7%), and three (7%) patients, respectively. During treatment, placental growth factor markedly increased, whereas vascular endothelial growth factor (VEGF)-A dramatically decreased (p < .0001); soluble VEGF receptor-2 (p < .0001) and CECs (p = .03) transiently increased on day 3. High and increased CEC counts at day 15 were associated with the ORR (p = .04) and the 16W-DCR (p = .02), respectively. Lower interleukin (IL)-8 levels at baseline (p = .01) and throughout treatment (p ≤ .04) were associated with the 16W-DCR. High baseline IL-8 and IL-6 levels predicted shorter progression-free and overall survival times (p ≤ .04). Conclusion. Bevacizumab is active and well tolerated in patients with advanced HCC. The clinical value of CECs, IL-6, and IL-8 warrants further investigation. PMID:22707516

  8. A framework of risk-informed seismic safety evaluation of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    A framework of risk-informed seismic design and safety evaluation of nuclear power plants is under consideration in Japan so as to utilize the progress in the seismic probabilistic safety assessment methodology. Issues resolved to introduce this framework are discussed after the concept, evaluation process and characteristics of the framework are described. (author)

  9. SAFETY

    CERN Multimedia

    Niels Dupont

    2013-01-01

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

  10. CRITICALITY HAZOP EFFICIENTLY EVALUATING HAZARDS OF NEW OR REVISED CRITICALITY SAFETY EVALUATIONS

    International Nuclear Information System (INIS)

    The 'Criticality HazOp' technique, as developed at Hanford's Plutonium Finishing Plant (PFP), has allowed for efficiencies enabling shortening of the time necessary to complete new or revised criticality safety evaluation reports (CSERs). For example, in the last half of 2007 at PFP, CSER revisions undergoing the 'Criticality HazOp' process were completed at a higher rate than previously achievable. The efficiencies gained through use of the 'Criticality HazOp' process come from the preliminary narrowing of potential scenarios for the Criticality analyst to fully evaluate in preparation of the new or revised CSER, and from the use of a systematized 'Criticality HazOp' group assessment of the relevant conditions to show which few parameter/condition/deviation combinations actually require analytical effort. The 'Criticality HazOp' has not only provided efficiencies of time, but has brought to criticality safety evaluation revisions the benefits of a structured hazard evaluation method and the enhanced insight that may be gained from direct involvement of a team in the process. In addition, involved personnel have gained a higher degree of confidence and understanding of the resulting CSER product

  11. Regulatory aspects of oncology drug safety evaluation: Past practice, current issues, and the challenge of new drugs

    International Nuclear Information System (INIS)

    The drug development of new anti-cancer agents is streamlined in response to the urgency of bringing effective drugs to market for patients with limited life expectancy. FDA's regulation of oncology drugs has evolved from the practices set forth in Arnold Lehman's seminal work published in the 1950s through the current drafting of a new International Conference on Harmonization of Technical Requirements for Registration of Pharmaceuticals for Human Use (ICH) safety guidance for anti-cancer drug nonclinical evaluations. The ICH combines the efforts of the regulatory authorities of Europe, Japan, and the United States and the pharmaceutical industry from these three regions to streamline the scientific and technical aspects of drug development. The recent development of new oncology drug classes with novel mechanisms of action has improved survival rates for some cancers but also brings new challenges for safety evaluation. Here we present the legacy of Lehman and colleagues in the context of past and present oncology drug development practices and focus on some of the current issues at the center of an evolving harmonization process that will generate a new safety guidance for oncology drugs, ICH S9. The purpose of this new guidance will be to facilitate oncology drug development on a global scale by standardizing regional safety requirements.

  12. Considerations on Safety Evaluation of Safety grade Smart Transmitter in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyung Tae; Jeong, Choong heui [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    Non-safety grade smart transmitters have been used for I and C systems of NPPs(Nuclear Power Plants). Smart transmitter is a microprocessor-based device including software and provides capability for digital signals to be communicated on top of the 4-20 mA analog signals. Recently, smart transmitters have been used for safety grade I and C systems as well as non-safety grade I and C system for SKN 3 and 4. Due to potential benefits of smart transmitter, it is anticipated smart transmitters will be widely used safety-related applications at NPPs. For those reasons, smart transmitter's technology and characteristics need to be investigated. Smart transmitters have been used for safety grade as well as non-safety grade I and C system since SKN 3 and 4. Due to potential benefits of smart transmitter, it is anticipated smart transmitters will be widely used safety-related applications at NPPs. For those reasons, smart transmitter's technology and characteristics need to be investigated. To get useful information about that, we surveyed EPRI qualification report, NRC event report, and SKN 3 and 4's review.

  13. Considerations on Safety Evaluation of Safety grade Smart Transmitter in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Non-safety grade smart transmitters have been used for I and C systems of NPPs(Nuclear Power Plants). Smart transmitter is a microprocessor-based device including software and provides capability for digital signals to be communicated on top of the 4-20 mA analog signals. Recently, smart transmitters have been used for safety grade I and C systems as well as non-safety grade I and C system for SKN 3 and 4. Due to potential benefits of smart transmitter, it is anticipated smart transmitters will be widely used safety-related applications at NPPs. For those reasons, smart transmitter's technology and characteristics need to be investigated. Smart transmitters have been used for safety grade as well as non-safety grade I and C system since SKN 3 and 4. Due to potential benefits of smart transmitter, it is anticipated smart transmitters will be widely used safety-related applications at NPPs. For those reasons, smart transmitter's technology and characteristics need to be investigated. To get useful information about that, we surveyed EPRI qualification report, NRC event report, and SKN 3 and 4's review

  14. Safety evaluation report related to operation of Fast Flux Test Facility. Supplement No. 1

    Energy Technology Data Exchange (ETDEWEB)

    1979-05-01

    This supplement provides (1) the staff's evaluation of additional information received since issuance of the Safety Evaluation Report regarding previously identified uncompleted review items, (2) a discussion of comments made by the ACRS in its report of November 8, 1978, and (3) the staff's evaluation of additional or revised information related to new or old issues that have arisen since the issuance of the Safety Evaluation Report.

  15. Evaluating Government's Policies on Promoting Smart Metering in Retail Electricity Markets via Agent Based Simulation

    OpenAIRE

    Zhang, Tao; Nuttall, William J.

    2008-01-01

    In this paper, we develop an agent-based model of a market game in order to evaluate the effectiveness of the UK government’s 2008-2010 policy on promoting smart metering. We also consider possible supplementary strategies. With the model, we test the effectiveness of four possible strategy options and suggest their policy implications. The context of the paper is a practical application of agent-based simulation to the retail electricity market in Britain. The contribution of the research ar...

  16. Performance Evaluation of Bidding-Based Multi-Agent Scheduling Algorithms for Manufacturing Systems

    Directory of Open Access Journals (Sweden)

    Antonio Gordillo

    2014-10-01

    Full Text Available Artificial Intelligence techniques have being applied to many problems in manufacturing systems in recent years. In the specific field of manufacturing scheduling many studies have been published trying to cope with the complexity of the manufacturing environment. One of the most utilized approaches is (multi agent-based scheduling. Nevertheless, despite the large list of studies reported in this field, there is no resource or scientific study on the performance measure of this type of approach under very common and critical execution situations. This paper focuses on multi-agent systems (MAS based algorithms for task allocation, particularly in manufacturing applications. The goal is to provide a mechanism to measure the performance of agent-based scheduling approaches for manufacturing systems under key critical situations such as: dynamic environment, rescheduling, and priority change. With this mechanism it will be possible to simulate critical situations and to stress the system in order to measure the performance of a given agent-based scheduling method. The proposed mechanism is a pioneering approach for performance evaluation of bidding-based MAS approaches for manufacturing scheduling. The proposed method and evaluation methodology can be used to run tests in different manufacturing floors since it is independent of the workshop configuration. Moreover, the evaluation results presented in this paper show the key factors and scenarios that most affect the market-like MAS approaches for manufacturing scheduling.

  17. The role of the nuclear regulator in promoting and evaluating safety culture

    International Nuclear Information System (INIS)

    The Committee on Nuclear Regulatory Activities (CNRA) of the OECD Nuclear Energy Agency (NEA) is an international body made up of senior representatives from nuclear regulatory bodies. The Committee guides the NEA's programme concerning the regulation, licensing and inspection of nuclear installations with respect to safety. It acts as a forum for the exchange of information and experience, and for the review of developments which could affect regulatory requirements. This report is the first in a series produced by the Task Group, and focuses on early signs of declining safety performance, and the role of the regulator in promoting and evaluating safety culture. The report contains the following issues: Importance of safety culture to nuclear safety; Role and attitude of regulator in promoting safety culture and in evaluating safety culture; Regulatory response strategies. (author)

  18. Evaluation of Safety, Quality and Productivity in Construction

    Science.gov (United States)

    Usmen, M. A.; Vilnitis, M.

    2015-11-01

    This paper examines the success indicators of construction projects, safety, quality and productivity, in terms of their implications and impacts during and after construction. First safety is considered during construction with a focus on hazard identification and the prevention of occupational accidents and injuries on worksites. The legislation mandating safety programs, training and compliance with safety standards is presented and discussed. Consideration of safety at the design stage is emphasized. Building safety and the roles of building codes in prevention of structural failures are also covered in the paper together with factors affecting building failures and methods for their prevention. Quality is introduced in the paper from the perspective of modern total quality management. Concepts of quality management, quality control, quality assurance and Six Sigma and how they relate to building quality and structural integrity are discussed with examples. Finally, productivity concepts are presented with emphasis on effective project management to minimize loss of productivity, complimented by lean construction and lean Six Sigma principles. The paper concludes by synthesizing the relationships between safety, quality and productivity.

  19. Safety evaluation of an extract from Salacia oblonga.

    Science.gov (United States)

    Wolf, B W; Weisbrode, S E

    2003-06-01

    Plant extracts from the Salacia genus have been found to have intestinal alpha-glucosidase inhibitor activity, which may have application to the development of medical foods for people with diabetes. We evaluated the safety of a hot water extract of S. oblonga (salacinol extract) supplemented to or processed into a medical food. Thirty male Sprague-Dawley rats were assigned among one of three treatments: (1) EN-0178 (control, liquid diet), (2) EN-0178+salacinol (as 1 plus 500 mg of salacinol extract per 253 g diet, which was added to product immediately prior to feeding), (3) EN-0195 (as 1 plus 500 mg of salacinol extract per 253 g diet, which was added during product manufacture). After 14 days of free access to dietary treatments, rats were sacrificed, blood collected and organs weighed. Rats consuming salacinol extract had reduced (P <0.05) weight gain and feed intake. The relative (% of body weight) testicular weight was higher (P<0.05) for rats consuming salacinol extract, whereas, the relative liver and spleen weight was lower (P<0.05) for rats consuming salacinol extract. Of the serum chemistries analyzed, blood urea nitrogen and alkaline phosphatase was lower (P<0.05) for rats consuming salacinol extract. No differences in blood hematology were found. We conclude that salacinol extract, in a medical food consumed for 2 weeks in amounts estimated at 10-fold greater than proposed for human intake, did not result in clinical chemistry or histopathologic indications of toxic effects in male Sprague-Dawley rats. PMID:12738192

  20. Evaluation of the efficiency and safety in cosmetic products.

    Science.gov (United States)

    Uckaya, Meryem; Uckaya, Fatih; Demir, Nazan; Demir, Yasar

    2016-02-29

    Chemicals used in cosmetics have to interact with enzymes for beneficial or destroy purpose after they enter in our body. Active sections of enzymes that catalyze reactions have three dimensions and they are active optically. When these limitations of catalytic sections are considered, it may be considered that defining geometric specifications of chemical materials and functional groups they contain may contribute on safety evaluations of cosmetic products. In this study, defining similarities and differences of geometric structures of chemicals that are prohibited to be used in cosmetic products and chemical that are allowed to be used by using group theory and analyze of functional groups that are often encountered in these chemicals are aimed. Molecule formulas related to chemical material of, 276 pieces chemicals that are prohibited to be used in cosmetic products and 65 pieces chemicals that are allowed, are used as the material. Two and three-dimension structures of these formulas are drawn and types and quantity of functional groups they contain are defined. And as a method, freeware (Free Trial) version of "Chem-BioOffice Ultra 13.0 Suite" chemical drawing program to draw two and three-dimension of formulas, "Campus-Licensed" version that are provided for use by our university of "Autodesk 3DS Max" for three-dimension drawings are used. In order to analyze geometric specifications of drawn molecules according to Group Theory and define type and quantity of available functional groups, Excel applications developed by Prof. Dr. Yaşar Demir are used. PMID:26773597

  1. Evaluation of syphilis serostatus on the safety of IVF treatment.

    Science.gov (United States)

    Lin, Shengli; Li, Rong; Huang, Shuo; Zhao, Lianming; Li, Ming; Li, Junsheng; Zhu, Jinliang; Zheng, Xiaoying; Huang, Jin; Liu, Ping; Qiao, Jie

    2014-12-01

    An increasing number of infertile syphilis-infected individuals have turned to assisted reproductive technology; however, the safety of syphilis carrier serostatus on IVF and embryo transfer outcomes has not been evaluated. Data from 482 patients who delivered singletons were analysed. In the retrospective study, the rate of IVF and intracytoplasmic sperm injection fertilization was 79.50% ± 17.57%/78.72% ± 16.66% in the Treponema pallidum particle agglutination assay negative (TPPA-negative) and rapid plasma reagin negative (RPR-negative) group, 76.12% ± 22.99%/74.05% ± 20.31% in the TPPA-positive and RPR-negative group, and 75.66% ± 21.72%/70.90% ± 16.11% in the TPPA-positive and RPR-positive group. The clinical pregnancy rate was 39.79% in the TPPA-negative and RPR-negative group, 46.30% in the TPPA-positive and RPR-negative group, and 36.59% in the TPPA-positive and RPR-positive group. No significant differences were found between the groups. The neonatal gestational age and mean birth weight were not significantly different between the TPPA-negative and TPPA-positive groups. Multiple linear regression analysis also showed no association between TPPA serostatus and newborn birth weight and gestational age. The present retrospective study showed that TPPA and RPR serostatus did not affect the outcomes of IVF and embryo transfer. Syphilis-infected individuals can undergo IVF and embryo transfer cycles after penicillin treatment. PMID:25444510

  2. PSA analysis focused on Mochovce NPP safety measures evaluation from operational safety point of view

    International Nuclear Information System (INIS)

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present two units are operated and another two are under the construction. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on the exploitation of similar units. These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for SMs establishing including their grouping covering different areas of safety goals and results of SM contributions to the total core damage frequency based on FPSA analysis. (author)

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

    International Nuclear Information System (INIS)

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

  4. Evaluation model for safety capacity of chemical industrial park based on acceptable regional risk

    Institute of Scientific and Technical Information of China (English)

    Guohua Chen; Shukun Wang; Xiaoqun Tan

    2015-01-01

    The paper defines the Safety Capacity of Chemical Industrial Park (SCCIP) from the perspective of acceptable regional risk. For the purpose of exploring the evaluation model for the SCCIP, a method based on quantitative risk assessment was adopted for evaluating transport risk and to confirm reasonable safety transport capacity of chemical industrial park, and then by combining with the safety storage capacity, a SCCIP evaluation model was put forward. The SCCIP was decided by the smaller one between the largest safety storage capacity and the maximum safety transport capacity, or else, the regional risk of the park will exceed the acceptable level. The developed method was applied to a chemical industrial park in Guangdong province to obtain the maximum safety transport capacity and the SCCIP. The results can be realized in the regional risk control of the park effectively.

  5. Evaluation of potential practical oral contrast agents for pediatric magnetic resonance imaging

    International Nuclear Information System (INIS)

    Development of a practical oral contrast agent for magnetic resonance imaging is necessary to improve differentiation of bowel from adjacent structures. In order to find a readily available, inexpensive, non-toxic, palatable solution for use in the pediatric population, several formulas, milk products and a common oral sedative were evaluated in vitro. T1, T2 and signal intensity measurements were performed on a 1.5 T system. Similac with standard iron proved to be a useful high signal intensity agent on multiple pulse sequences. Early in vivo experience in four normal volunteers indicates that this agent provides excellent delineation of the stomach and duodenum from contiguous viscera. Distal small bowel visualization is less predictabel. Further clinical trials should confirm the utility of this solution, which contains a combination of iron salts and paramagnetic metallic ions. (orig.)

  6. Meteorological events in site evaluation for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    This Safety Guide provides recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. It is of interest to safety assessors and regulators involved in the licensing process as well as to designers of nuclear power plants. This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It supplements the IAEA Safety Requirements publication on Site Evaluation for Nuclear Facilities which is to supersede the Code on the Safety of Nuclear Power Plants: Siting, Safety Series No. 50-C-S (Rev. 1), IAEA, Vienna (1988). The present Safety Guide supersedes two earlier Safety Guides: Safety Series No. 50-SG-S11A (1981) on Extreme Meteorological Events in Nuclear Power Plant Siting, Excluding Tropical Cyclones and Safety Series No. 50-SG-S11B (1984) on Design Basis Tropical Cyclone for Nuclear Power Plants. The purpose of this Safety Guide is to provide recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. This Safety Guide provides interpretation of the Safety Requirements publication on Site Evaluation for Nuclear Facilities and guidance on how to fulfil these requirements. It is aimed at safety assessors or regulators involved in the licensing process as well as designers of nuclear power plants, and provides them with guidance on the methods and procedures for analyses that support the assessment of the hazards associated with extreme and rare meteorological events. This Safety Guide discusses the extreme values of meteorological variables and rare meteorological phenomena, as well as their rates of occurrence, according to the following definitions: (a) Extreme values of meteorological variables such as air temperature and wind speed characterize the meteorological or climatological environment; and (b) Rare meteorological phenomena

  7. Report of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. Result evaluation in fiscal year 2000

    International Nuclear Information System (INIS)

    The Research Evaluation Committee, which consisted of 14 members from outside of the Japan Atomic Energy Research Institute (JAERI), set up an Ad Hoc Review Committee on Nuclear Safety Research in accordance with the Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations in order to evaluate the R and D accomplishments achieved for five years from Fiscal Year 1995 to Fiscal Year 1999 at Department of Reactor Safety Research, Department of Fuel Cycle Safety Research, Department of Environmental Safety Research and Department of Safety Research Technical Support in Tokai Research Establishment at JAERI. The Ad Hoc Review Committee consisted of 11 specialists from outside of JAERI. The Ad Hoc Review Committee conducted its activities from December 2000 to February 2001. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Ad Hoc Review Committee meeting which was held on December 11, 2000, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Ad Hoc Review Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on March 16, 2001. This report describes the result of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. (author)

  8. The evaluation of the nuclear facilities safety at the CEA from 1999 to 2001

    International Nuclear Information System (INIS)

    The aim of this document is the presentation of an evaluation of the problems and the safety methods in the concerned period. The first chapter presents the nuclear safety in the CEA. The second chapter is devoted to the organization and the quality for the safety: liabilities, audits, relations with the safety authorities and with the public. The chapters three and four deal respectively with the methodological and technical abilities supporting the exploitation teams and with the nuclear safety projects. The last chapter presents the experiments and events from 1999 to 2001. (A.L.B.)

  9. Safety culture evaluation and asset root cause analysis

    International Nuclear Information System (INIS)

    This paper examines the role of organizational and management factors in nuclear power plant safety through the use of operating experiences. The ASSET reports of thirteen plants (total thirty events) have been analyzed in term of twenty organizational dimensions (factors) identified by Brookhaven National Laboratory and Pennsylvania State University. For three plants detailed results are reported in this paper. The results of thirteen plants are summarized in the form of a table. The study tends to confirm that organizational and management factors play an important role in plant safety. The twenty organizational dimensions and their definitions, in general, were adequate in this study. Formalization, safety culture, technical knowledge, training, roles-responsibilities and problem identification appear to be key organizational factors which influence the safety of nuclear power plants studied. (author)

  10. Safety evaluation for the inner canister closure station

    International Nuclear Information System (INIS)

    The Inner Canister Closure Station (ICCS), built by Remote Technology Corporation, will be operability tested. The ICCS is used to remotely leak test Inner Canister Closures (ICC's) and replace ICC's that are not water tight. After operability testing, the ICCS will be inspected and sent to the 717-F mock-up shop for remotability demonstration and dimensional checks, then installed in the Vitrification Building, 221-S. An analysis of potential safety hazards, equipment safety features, and procedural controls indicates that the ICCS can be operated without undue hazard to employees or to the public. A safety inspection and a new equipment inspection will be held before operation to verify that the ICCS meets Savannah River Site safety requirements. 4 refs., 6 figs

  11. Safety

    International Nuclear Information System (INIS)

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

  12. Evaluation of the implementation of a four-year national hospital patient safety program in the Netherlands.

    OpenAIRE

    Schilp, J.; Blok, C.; Wagner, C.

    2013-01-01

    Objectives: To evaluate the implementation of five safety themes within a four-year national hospital patient safety program in the Netherlands. Methods: In 2008, a national hospital patient safety program was started to improve patient safety in Dutch hospitals. The safety program focussed on 10 safety themes, chosen through consultation with experts in the relevant professional groups and medical specialism. For each safety theme a module was developed to support hospitals with the implemen...

  13. ECORA - Evaluation of Computational Methods for Reactor Safety Analysis

    International Nuclear Information System (INIS)

    There were three motivations behind the ECORA Project: - the shortcomings of 0-D system codes in the simulation of 3-D, local flow and heat transfer phenomena, - increased interest in the application of 3-D CFD software as supplement to system codes, - high safety requirements in the nuclear industry required consistent standards for the use and assessment of CFD software. The purpose of ECORA was therefore: - to establish performance criteria for the assessment of CFD software, - to establish Best Practice Guidelines for application and use of CFD software, with the following objectives: - assessment of CFD applications in reactor safety: flows in containment (PANDA experiments) and flows in primary system (UPTF experiments) - Best Practice Guidelines for reactor safety: starting point (ERCOFTAC Best Practice Guidelines), adaptation to CFD application for nuclear safety, extension to assessment of experimental data - recommendations for improvements of CFD software, - network of European 'Centres of Competence for CFD Applications in Reactor Safety'. Currently, there were twelve partners in the ECORA Project, representing nine European countries. The Project was scheduled to last until September 2004. Ms Scheuerer then described the work programme and project structure, the Best Practice Guidelines for CFD simulations, the procedures for quantifying errors, applications of Best Practice Guidelines, Best Practice Guidelines for experimental data, applications to primary system, UPTF and PANDA data. Her conclusions were the following: - the Project had led to the improvement of the quality of CFD calculations in reactor safety, through: the ECORA Best Practice Guidelines, the assessment of shortcomings and the improvement of mathematical models. - It had also led to higher acceptance of CFD in reactor safety. - The next step was the establishment of European 'Centres of Competence for CFD Applications in reactor Safety'

  14. Evaluating a Telenovela: The Safety of Latino Construction Workers

    OpenAIRE

    Castaneda, Diego Emiliano

    2011-01-01

    Latino-Hispanic construction workers in the United States are at significantly higher risks for injuries and fatalities at construction worksites than their White and African-American counterparts. Currently the main mode of dissemination of workplace safety information is through direct translation of work safety material delivered at the worksite. Current research, however, suggests that even when translated into Spanish, many of these materials are not culturally or linguistically effectiv...

  15. I feel you: the design and evaluation of a domotic affect-sensitive spoken conversational agent.

    Science.gov (United States)

    Lutfi, Syaheerah Lebai; Fernández-Martínez, Fernando; Lorenzo-Trueba, Jaime; Barra-Chicote, Roberto; Montero, Juan Manuel

    2013-01-01

    We describe the work on infusion of emotion into a limited-task autonomous spoken conversational agent situated in the domestic environment, using a need-inspired task-independent emotion model (NEMO). In order to demonstrate the generation of affect through the use of the model, we describe the work of integrating it with a natural-language mixed-initiative HiFi-control spoken conversational agent (SCA). NEMO and the host system communicate externally, removing the need for the Dialog Manager to be modified, as is done in most existing dialog systems, in order to be adaptive. The first part of the paper concerns the integration between NEMO and the host agent. The second part summarizes the work on automatic affect prediction, namely, frustration and contentment, from dialog features, a non-conventional source, in the attempt of moving towards a more user-centric approach. The final part reports the evaluation results obtained from a user study, in which both versions of the agent (non-adaptive and emotionally-adaptive) were compared. The results provide substantial evidences with respect to the benefits of adding emotion in a spoken conversational agent, especially in mitigating users' frustrations and, ultimately, improving their satisfaction. PMID:23945740

  16. Evaluation of oxime efficacy in nerve agent poisoning: Development of a kinetic-based dynamic model

    International Nuclear Information System (INIS)

    The widespread use of organophosphorus compounds (OP) as pesticides and the repeated misuse of highly toxic OP as chemical warfare agents (nerve agents) emphasize the necessity for the development of effective medical countermeasures. Standard treatment with atropine and the established acetylcholinesterase (AChE) reactivators, obidoxime and pralidoxime, is considered to be ineffective with certain nerve agents due to low oxime effectiveness. From obvious ethical reasons only animal experiments can be used to evaluate new oximes as nerve agent antidotes. However, the extrapolation of data from animal to humans is hampered by marked species differences. Since reactivation of OP-inhibited AChE is considered to be the main mechanism of action of oximes, human erythrocyte AChE can be exploited to test the efficacy of new oximes. By combining enzyme kinetics (inhibition, reactivation, aging) with OP toxicokinetics and oxime pharmacokinetics a dynamic in vitro model was developed which allows the calculation of AChE activities at different scenarios. This model was validated with data from pesticide-poisoned patients and simulations were performed for intravenous and percutaneous nerve agent exposure and intramuscular oxime treatment using published data. The model presented may serve as a tool for defining effective oxime concentrations and for optimizing oxime treatment. In addition, this model can be useful for the development of meaningful therapeutic animal models

  17. I Feel You: The Design and Evaluation of a Domotic Affect-Sensitive Spoken Conversational Agent

    Directory of Open Access Journals (Sweden)

    Juan Manuel Montero

    2013-08-01

    Full Text Available We describe the work on infusion of emotion into a limited-task autonomous spoken conversational agent situated in the domestic environment, using a need-inspired task-independent emotion model (NEMO. In order to demonstrate the generation of affect through the use of the model, we describe the work of integrating it with a natural-language mixed-initiative HiFi-control spoken conversational agent (SCA. NEMO and the host system communicate externally, removing the need for the Dialog Manager to be modified, as is done in most existing dialog systems, in order to be adaptive. The first part of the paper concerns the integration between NEMO and the host agent. The second part summarizes the work on automatic affect prediction, namely, frustration and contentment, from dialog features, a non-conventional source, in the attempt of moving towards a more user-centric approach. The final part reports the evaluation results obtained from a user study, in which both versions of the agent (non-adaptive and emotionally-adaptive were compared. The results provide substantial evidences with respect to the benefits of adding emotion in a spoken conversational agent, especially in mitigating users’ frustrations and, ultimately, improving their satisfaction.

  18. Periodic safety re-evaluations in NPPs in EC member states, Finland and Sweden

    International Nuclear Information System (INIS)

    The work on periodic safety re-evaluations summarized in this report was performed by a Task Force of the CEC Working Group on the Safety of Thermal Reactors. The periodic safety re-evaluations under review in this study were those that are carried out in addition to other reviews which represent the primary means of safety assurance. The periodic safety re-evaluation is broader and more comprehensive in nature. The cumulative effects of experience (national and international), advances in knowledge and analysis techniques, improvements in safety standards and operating practices, overall effects of plant ageing, and the totality of all modifications over the period in question need to be taken into account. All countries have recognized the value of such periodic reviews, and licensees, either as a regulatory requirement or as a voluntary action, are carrying them out. The scope and contents of each country's review showed many similarities of approach, any differences being explained by the age and type of reactor in operation. Many similarities emerged in the topics selected for re-evaluation and in the approach to re-evaluation itself. The overall conclusion was that while approaches may differ in some respects, for practical purposes comparable levels of safety are achieved in the periodic safety re-evaluation of nuclear power plants

  19. Application of Mixed Group Decision Making to Safety Evaluation of Agricultural Products

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    In view of the gravity of issues concerning safety of agricultural products and urgency of resolving these issues,after analyzing the problems existing in safety of agricultural products,this article offers a method for evaluating safety of agricultural products on the basis of mixed group decision making.First of all,it introduces the factors influencing safety evaluation of agricultural products;subsequently,given that the judgment matrices offered by the group of experts contain both reciprocal and complementary judgment matrices in the process of jointly participating in evaluation arising from personal preference,it proposes to assemble expert information in order to obtain indicator weight using the OWA operator;finally,the process of evaluating safety of agricultural products is given.

  20. PSA analysis focused on Mochovce NPP safety measures evaluation from operational safety point of view

    International Nuclear Information System (INIS)

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing.(author)

  1. Mochovce NPP safety measures evaluation from point of view of operational safety enhancement

    International Nuclear Information System (INIS)

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing. (author)

  2. Safety Comprehensive Evaluation of Spacecraft Assembly Process Based on Grey-Fuzzy Method

    OpenAIRE

    Jin Tian; Ju Fu

    2014-01-01

    Multilevel evaluation indicator system for spacecraft assembly safety was built, considering six aspects: operators, process equipment, operating environment, operation types, objects to be operated, and emergency measures. Based on that, a grey-fuzzy comprehensive evaluation approach was proposed to support the spacecraft assembly safety evaluation. In the approach, analytic hierarchy process and grey degree were applied to construct weight matrix, and the principle with which the appropriat...

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

    International Nuclear Information System (INIS)

    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)

  4. Evaluation of safety, an unavoidable requirement in the applications of ionizing radiations

    International Nuclear Information System (INIS)

    The safety assessments should be conducted as a means to evaluate compliance with safety requirements (and thus the application of fundamental safety principles) for all facilities and activities in order to determine the measures to be taken to ensure safety. It is an essential tool in decision making. For long time we have linked the safety assessment to nuclear facilities and not to all practices involving the use of ionizing radiation in daily life. However, the main purpose of the safety assessment is to determine if it has reached an appropriate level of safety for an installation or activity and if it has fulfilled the objectives of safety and basic safety criteria set by the designer, operating organization and the regulatory body under the protection and safety requirements set out in the International Basic safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. This paper presents some criteria and personal experiences with the new international recommendations on this subject and its practical application in the region and demonstrates the importance of this requirement. Reflects the need to train personnel of the operator and the regulatory body in the proportional application of this requirement in practice with ionizing radiation

  5. Occupational health and safety: Designing and building with MACBETH a value risk-matrix for evaluating health and safety risks

    Science.gov (United States)

    Lopes, D. F.; Oliveira, M. D.; Costa, C. A. Bana e.

    2015-05-01

    Risk matrices (RMs) are commonly used to evaluate health and safety risks. Nonetheless, they violate some theoretical principles that compromise their feasibility and use. This study describes how multiple criteria decision analysis methods have been used to improve the design and the deployment of RMs to evaluate health and safety risks at the Occupational Health and Safety Unit (OHSU) of the Regional Health Administration of Lisbon and Tagus Valley. ‘Value risk-matrices’ (VRMs) are built with the MACBETH approach in four modelling steps: a) structuring risk impacts, involving the construction of descriptors of impact that link risk events with health impacts and are informed by scientific evidence; b) generating a value measurement scale of risk impacts, by applying the MACBETH-Choquet procedure; c) building a system for eliciting subjective probabilities that makes use of a numerical probability scale that was constructed with MACBETH qualitative judgments on likelihood; d) and defining a classification colouring scheme for the VRM. A VRM built with OHSU members was implemented in a decision support system which will be used by OHSU members to evaluate health and safety risks and to identify risk mitigation actions.

  6. Evaluation of selected neutralizing agents for the treatment of uranium tailings leachates. Laboratory progress report

    International Nuclear Information System (INIS)

    Laboratory experiments were conducted to evaluate the performance of selected neutralizing agents for the treatment of uranium tailings solutions. Highly acidic tailings solutions (pH3) reagent grade; Calcium hydroxide [Ca(OH)2] reagent grade; Magnesium oxide (MgO) reagent grade; Sodium carbonate (Na2CO3) reagent grade; and Sodium hydroxide (NaOH) reagent grade. Evaluation of the effectiveness for the treatment of uranium tailings solutions for the selected neutralizing agents under controlled laboratory conditions was based on three criteria. The criteria are: (1) treated effluent water quality, (2) neutralized sludge handling and hydraulic properties, and (3) reagent costs and acid neutralizing efficiency. On the basis of these limited laboratory results calcium hydroxide or its dehydrated form CaO (lime) appears to be the most effective option for treatment of uranium tailings solutions

  7. Evaluation of behaviour and Safety in a geologic deep repository

    International Nuclear Information System (INIS)

    This report presents a comprehensive description of the post-closure radiological safety assessment of a repository for the spent fuel arisings resulting from the Spanish nuclear program. This Safety Assessment constitutes a first step within a systematical process that will permit, thorough successive approximations, to predict the performance of the different barriers of the disposal system, and its capability to comply with the assigned safety functions and with the established safety criteria. The primary bases for this Safety Assessment are the following: The disposal concept considers the storage of the fuel assemblies in carbon steel canisters of 10 cm of thickness, emplaced horizontally in galleries excavated in granite of 2,4 m of diameter and 500 m of length, using a bentonite thickness of 75 cm around canisters as buffer material. The repository is located in a granitic site defined with available data about surface characteristics of Spanish granites. The exercise uses a probabilistic approximation in order to cope with the uncertainties associated with the different imputs parameters. (Author)

  8. Development of the evaluation methods in reactor safety analyses and core characteristics

    International Nuclear Information System (INIS)

    In order to support the safety reviews by NISA on reactor safety design, the computer codes are developed and maintained in the areas of safety analyses and core characteristics evaluation. In the code preparation of safety analyses, the TRACE code was prepared to conduct the safety analysis of LOCA for PWR. Also, the statistical safety evaluation method based on the three-dimensional neutron-kinetics/thermal-hydraulics coupled code SKETCH/TRACE has been prepared. In the core physics code preparation, the advanced neutron data library JENDL-4.0 were incorporated in the lattice physics code CASMO-4. The verification of improved CASMO-4 /SIMULATE-3 was continued by using core physics data. (author)

  9. Development of the evaluation methods in reactor safety analyses and core characteristics

    International Nuclear Information System (INIS)

    In order to support the safety reviews by NISA on reactor safety design, the computer codes are developed and maintained in the areas of safety analyses and core characteristics evaluation. In the code preparation of safety analyses, the TRACE code was prepared to conduct the safety analysis of LOCA for APWR. Also, the statistical safety evaluation method based on the three-dimensional neutron-kinetics/thermal-hydraulics coupled code SKETCH/TRACE was prepared. In the core physics code preparation, the advanced neutron data library JENDL-3.3 and expanded nuclide chains were incorporated in the lattice physics code CASMO-4. The verification of improved CASMO-4 was continued by using core physics data. (author)

  10. Scale development of safety management system evaluation for the airline industry.

    Science.gov (United States)

    Chen, Ching-Fu; Chen, Shu-Chuan

    2012-07-01

    The airline industry relies on the implementation of Safety Management System (SMS) to integrate safety policies and augment safety performance at both organizational and individual levels. Although there are various degrees of SMS implementation in practice, a comprehensive scale measuring the essential dimensions of SMS is still lacking. This paper thus aims to develop an SMS measurement scale from the perspective of aviation experts and airline managers to evaluate the performance of company's safety management system, by adopting Schwab's (1980) three-stage scale development procedure. The results reveal a five-factor structure consisting of 23 items. The five factors include documentation and commands, safety promotion and training, executive management commitment, emergency preparedness and response plan and safety management policy. The implications of this SMS evaluation scale for practitioners and future research are discussed. PMID:22405247

  11. An approach using multi-factor combination to evaluate high rocky slope safety

    Science.gov (United States)

    Su, Huaizhi; Yang, Meng; Wen, Zhiping

    2016-06-01

    A high rocky slope is an open complex giant system for which there is contradiction among different influencing factors and coexistence of qualitative and quantitative information. This study presents a comprehensive intelligent evaluation method of high rocky slope safety through an integrated analytic hierarchy process, extension matter element model and entropy weight to assess the safety behavior of the high rocky slope. The proposed intelligent evaluation integrates subjective judgments derived from the analytic hierarchy process with the extension matter model and entropy weight into a multiple indexes dynamic safety evaluation approach. A combined subjective and objective comprehensive evaluation process, a more objective study, through avoiding subjective effects on the weights, and a qualitative safety assessment and quantitative safety amount are presented in the proposed method. The detailed computational procedures were also provided to illustrate the integration process of the above methods. Safety analysis of one high rocky slope is conducted to illustrate that this approach can adequately handle the inherent imprecision and contradiction of the human decision-making process and provide the flexibility and robustness needed for the decision maker to better monitor the safety status of a high rocky slope. This study was the first application of the proposed integrated evaluation method in the safety assessment of a high rocky slope. The study also indicated that it can also be applied to other similar problems.

  12. Evaluation of biological control agents for managing cucurbit powdery mildew on greenhouse-grown melon

    OpenAIRE

    Torés Montosa, Juan Antonio

    2007-01-01

    An evaluation was made of the ability of two mycoparasite-based products AQ10® (Ampelomyces quisqualis) and Mycotal® (Lecanicillium lecanii), as well as three strains of Bacillus subtilis, to manage powdery mildew disease, caused by Podosphaera fusca on melon seedlings maintained under different regimes of relative humidity and on plants grown under greenhouse conditions in Spain. In every case fungal and bacterial biocontrol agents (BCAs) performed better under conditions of high relative hu...

  13. Quantitative Evaluation of Contamination on Dental Zirconia Ceramic by Silicone Disclosing Agents after Different Cleaning Procedures

    OpenAIRE

    Sebastian Wille; Vincent van Broeck; Thomas Strunskus; Franz Faupel; Matthias Kern

    2015-01-01

    The aim of this study was to evaluate the effectiveness of cleaning procedures for air-abraded zirconia after contamination with two silicone disclosing agents. Air-abraded zirconia ceramic specimens (IPS e.max ZirCAD) were contaminated with either GC Fit Checker white or GC Fit Checker II. Untreated zirconia specimens were used as control. Afterwards the surfaces were cleaned either with waterspray or ultrasonically in 99% isopropanol or using a newly developed cleaning paste (Ivoclean). Aft...

  14. Synthesis and In Vitro Evaluation of New Thiosemicarbazone Derivatives as Potential Antimicrobial Agents

    OpenAIRE

    Zafer Asım Kaplancıklı; Mehlika Dilek Altıntop; Belgin Sever; Zerrin Cantürk; Ahmet Özdemir

    2016-01-01

    In an effort to develop potent antimicrobial agents, new thiosemicarbazone derivatives were synthesized via the reaction of 4-[4-(trifluoromethyl)phenyl]thiosemicarbazide with aromatic aldehydes. The compounds were evaluated for their inhibitory effects on pathogenic bacteria and yeasts using the CLSI broth microdilution method. Microplate Alamar Blue Assay was also carried out to determine the antimycobacterial activities of the compounds against Mycobacterium tuberculosis H37Rv. Among these...

  15. Comparative evaluation of two commercially available desensitizing agents for the treatment of dentinal hypersensitivity

    OpenAIRE

    Nymphea Pandit; Rajan Gupta; Aarti Bansal

    2012-01-01

    Aims: A randomized clinical trail was designed to compare the efficacy of two commercially available desensitizing agents (fluoride varnish containing 6% sodium fluoride and 6% calcium fluoride and a gel containing 6% potassium nitrate and 0.11% fluoride ions) in the treatment of dentinal hypersensitivity. Settings and Design: Randomized clinical trial. Materials and Methods: Twenty-one patients were selected. Subjects were evaluated using three different stimuli, i.e., tactile test, ai...

  16. Evaluating affective feedback of the 3D agent Max in a competitive cards game

    OpenAIRE

    Becker-Asano, Christian; Prendinger, Helmut; Ishizuka, Mitsuro; Wachsmuth, Ipke; Tao, Jianhua; Tan, Tieniu; Picard, Rosalind W.

    2005-01-01

    Within the field of Embodied Conversational Agents (ECAs), the simulation of emotions has been suggested as a means to enhance the believability of ECAs and also to effectively contribute to the goal of more intuitive human–computer interfaces. Although various emotion models have been proposed, results demonstrating the appropriateness of displaying particular emotions within ECA applications are scarce or even inconsistent. Worse, questionnaire methods often seem insufficient to evaluate th...

  17. Synthesis and evaluation of nitrate derivatives of colchicine as anticancer agents

    Institute of Scientific and Technical Information of China (English)

    Li Hong Shen; Ya Li; Da Hai Zhang; Yi Sheng Lai; Li Jie Liu

    2011-01-01

    To search for more potent antitumor agent, a series of novel nitric oxide-donating colchicine (Col) derivatives (6a-f, 8a and b) were synthesized by coupling nitrates with N-methyl colchiceinamide. Their cytotoxicity against four human cancer cell lines in vitro were evaluated by MTT assay. It was found that many of the derivatives displayed significant activity, particularly, compounds 6c, 8a and 8b showed more potent cytotoxic activities than Col.

  18. A Comparative Evaluation of Hydroxyapatite Crystals and Glutaraldehyde as Agents for Pulpotomy in Deciduous Molars

    OpenAIRE

    ADLAKHA, Vivek Kumar; Chandna, Preetika; Joshi, JL; Thomas, AM; Singh, Namita

    2009-01-01

    Purpose: To evaluate and compare clinically and radiographically use of hydroxyapatite crystals and 2% glutaraldehyde as a pulpotomy agent. Method: Thirty deciduous molars were treated with pulpotomy using hydroxyapatite crystals and 2% glutaraldehyde. Results: Clinical and radiographic findings were observed at three months and six months. The success rate was found to be 100% clinically and 80.33% radiographically in the hydroxyapatite crystals group and 100% clinically and radiographically...

  19. Equivalency Evaluation between IAEA Safety Guidelines and Codes and Standards for Computer-Based Systems

    International Nuclear Information System (INIS)

    Computer based systems are used in safety related applications in safety critical applications as well as safety related applications, such as reactor protection or actuation of safety features, certain functions of the process control and monitoring system. In this context, the IAEA released the safety standard series, NS-G-1.11 (hereafter: IAEA Guideline), 'Software for Computer Based Systems Important to Safety in NPPs', in 2000 as a guideline for evaluating the software of digitalized computer based system applied in instrumentation and control system of nuclear plants. This paper discusses about the equivalency between IAEA Guideline and codes and standards adopted by Korea Institute Nuclear Safety (hereafter: KINS Guideline) as regulatory basis. (authors)

  20. Evaluation of food safety management systems in Serbian dairy industry

    Directory of Open Access Journals (Sweden)

    Igor Tomašević

    2016-01-01

    Full Text Available This paper reports incentives, costs, difficulties and benefits of food safety management systems implementation in the Serbian dairy industry. The survey involved 27 food business operators with the national milk and dairy market share of 65 %. Almost two thirds of the assessed dairy producers (70.4 % claimed that they had a fully operational and certified HACCP system in place, while 29.6 % implemented HACCP, but had no third party certification. ISO 22000 was implemented and certified in 29.6 % of the companies, while only 11.1 % had implemented and certified IFS standard. The most important incentive for implementing food safety management systems for Serbian dairy producers was to increase and improve safety and quality of dairy products. The cost of product investigation/analysis and hiring external consultants were related to the initial set-up of food safety management system with the greatest importance. Serbian dairy industry was not greatly concerned by the financial side of implementing food safety management systems due to the fact that majority of prerequisite programmes were in place and regularly used by almost 100 % of the producers surveyed. The presence of competency gap between the generic knowledge for manufacturing food products and the knowledge necessary to develop and implement food safety management systems was confirmed, despite the fact that 58.8 % of Serbian dairy managers had university level of education. Our study brings about the innovation emphasizing the attitudes and the motivation of the food production staff as the most important barrier for the development and implementation of HACCP. The most important identified benefit was increased safety of dairy products with the mean rank scores of 6.85. The increased customer confidence and working discipline of staff employed in food processing were also found as important benefits of implementing/operating HACCP. The study shows that the level of HACCP

  1. Guideline on evaluation and acceptance of commercial grade digital equipment for nuclear safety applications

    International Nuclear Information System (INIS)

    Nuclear power plants are increasingly upgrading their instrumentation and control (I ampersand C) systems with commercial digital equipment, which allows them to continue meeting safety and reliability requirements while controlling operating costs. However, the use of commercial software-based devices for safety related applications has raised new issues that impact design, procurement, and licensing activities. This guideline describes a consistent, comprehensive approach for the evaluation and acceptance of commercial digital equipment for nuclear safety systems

  2. Evaluation procedure of software safety plan for digital I and C of KNGR

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo; Park, Jong Kyun; Lee, Ki Young; Kwon, Ki Choon; Kim, Jang Yeol; Cheon, Se Woo

    2000-05-01

    The development, use, and regulation of computer systems in nuclear reactor instrumentation and control (I and C) systems to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Korean next generation reactor (KNGR) software safety verification and validation (SSVV) task, Korea Atomic Energy Research Institute, which investigates different aspects of computer software in reactor I and C systems, and describes the engineering procedures for developing such a software. The purpose of this guideline is to give the software safety evaluator the trail map between the code and standards layer and the design methodology and documents layer for the software important to safety in nuclear power plants. Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organizations. The requirements for software important to safety of nuclear reactor are described in such positions and standards, for example, the new standard review plan (SRP), IEC 880 supplements, IEEE standard 1228-1994, IEEE standard 7-4.3.2-1993, and IAEA safety series No. 50-SG-D3 and D8. We presented the guidance for evaluating the safety plan of the software in the KNGR protection systems. The guideline consists of the regulatory requirements for software safety in chapter 2, the evaluation checklist of software safety plan in chapter3, and the evaluation results of KNGR software safety plan in chapter 4.

  3. RETRAN analysis of Safety Relief Valve setpoint - drift and tolerance evaluation for BWRs

    International Nuclear Information System (INIS)

    This study presents implications and guidelines for safety evaluations of Safety Relief Valve setpoint drift in a GE BWR/4 design reactor. The problem was investigated using the RETRAN02MOD003 code. The analysis demonstrated that margin to the safety limit pressure is maintained even for the extreme case of one SRV out-of-service with the remaining actuating at 5% above setpoint pressure

  4. Evaluation procedure of software safety plan for digital I and C of KNGR

    International Nuclear Information System (INIS)

    The development, use, and regulation of computer systems in nuclear reactor instrumentation and control (I and C) systems to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Korean next generation reactor (KNGR) software safety verification and validation (SSVV) task, Korea Atomic Energy Research Institute, which investigates different aspects of computer software in reactor I and C systems, and describes the engineering procedures for developing such a software. The purpose of this guideline is to give the software safety evaluator the trail map between the code and standards layer and the design methodology and documents layer for the software important to safety in nuclear power plants. Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organizations. The requirements for software important to safety of nuclear reactor are described in such positions and standards, for example, the new standard review plan (SRP), IEC 880 supplements, IEEE standard 1228-1994, IEEE standard 7-4.3.2-1993, and IAEA safety series No. 50-SG-D3 and D8. We presented the guidance for evaluating the safety plan of the software in the KNGR protection systems. The guideline consists of the regulatory requirements for software safety in chapter 2, the evaluation checklist of software safety plan in chapter3, and the evaluation results of KNGR software safety plan in chapter 4

  5. French statutory approach of the evaluation of the safety level of old nuclear divisions

    International Nuclear Information System (INIS)

    The legal French procedures include three steps which have to be followed during the exam of the safety in nuclear plants (creation authorization, loading authorization, actual running of the plant). After listing the different types of evaluation of safety in fraction of plants, this report presents the main themes encountered during the safety assessment: state of the reactor, maintenance, tracking of the incidents, personnel training, radioprotection, radioactive releases. The Fessenheim and Bugey list of reevaluation themes is also given. (TEC)

  6. From human errors to drivers' needs: An evaluation of the potential effectiveness of safety functions

    OpenAIRE

    VAN ELSLANDE, Pierre

    2011-01-01

    A specific contribution to evaluation of safety functions efficiency directed toward road user's needs, a methodology taking into account human difficulties (functional failures) and accident reality (context parameters), allow defining: Safety needs for different kinds of drivers, reflecting their accident-generating failures at the different stage of the process ; The potential capacity of safety functions to meet these needs ; The potential lacks in the functions efficiency ; The condition...

  7. Postearthquake safety evaluation of buildings at DOE (Department of Energy) facilities

    International Nuclear Information System (INIS)

    New postearthquake building safety evaluation procedures have been developed. The procedures cover inspection and safety assessment of the principal types of building construction found in the US, including wood, masonry, tilt-up, concrete, and steel frame structures. Guidelines are also provided for appraising the structural safety significance of ground movements resulting from geologic hazards and for the inspection of nonstructural elements for falling and other hazards

  8. Synthesis and evaluation of new protecting agents against ionizing radiations; Synthese et evaluation de nouveaux agents de protection contre les rayonnements ionisants

    Energy Technology Data Exchange (ETDEWEB)

    Nadal, B.

    2009-10-15

    This thesis is devoted to the synthesis of new pulvinic acid derivatives and the evaluation of their antioxidant and radioprotective properties. This study has been conducted with the aim to develop new protecting agents against ionizing radiations. A new access to pulvinic acid derivatives was developed starting from L-dimethyl tartrate. It is based on a Dieckmann cyclization a dehydration and a Suzuki-Miyaura coupling. It allows a short effective preparation of various pulvinic acid derivatives: tetronic acid derivatives, mono-substituted pulvinic acid derivatives and methyl pulvinates. A modified method has been used to prepare pulvinones. This strategy gave access in four steps to the desired pulvinones. The rapidity of this method is provided by a tandem process, carried out in the final step, involving a Dieckmann cyclization and a {beta}-elimination. A synthesis of 3-aryltetramic acids has also been developed in order to prepare nitrogen derivatives of pulvinic acid. The antioxidant activity of the prepared compounds was then evaluated using various tests: DPPH, ABTS, protection of thymidine and DNA study of lipid peroxidation. These evaluations allowed to define interesting structure-activity relationships of pulvinic derivatives. They have shown that several derivatives have very good antioxidant activities. Finally, radioprotective tests on TK6 cells and mice have have been performed on selected compounds. (author)

  9. Stakeholders' Perspectives About and Priorities for Economic Evaluation of Health and Safety Programs in Healthcare.

    Science.gov (United States)

    Tompa, Emile; de Boer, Henriette; Macdonald, Sara; Alamgir, Hasanat; Koehoorn, Mieke; Guzman, Jaime

    2016-04-01

    This study identified and prioritized resources and outcomes that should be considered in more comprehensive and scientifically rigorous health and safety economic evaluations according to healthcare sector stakeholders. A literature review and stakeholder interviews identified candidate resources and outcomes and then a Delphi panel ranked them. According to the panel, the top five resources were (a) health and safety staff time; (b) training workers; (c) program planning, promotion, and evaluation costs; (d) equipment purchases and upgrades; and (e) administration costs. The top five outcomes were (a) number of injuries, illnesses, and general sickness absences; (b) safety climate; (c) days lost due to injuries, illnesses, and general sickness absences; (d) job satisfaction and engagement; and (e) quality of care and patient safety. These findings emphasize stakeholders' stated priorities and are useful as a benchmark for assessing the quality of health and safety economic evaluations and the comprehensiveness of these findings. PMID:27056937

  10. The use of non-animal alternatives in the safety evaluations of cosmetics ingredients by the Scientific Committee on Consumer Safety (SCCS)

    OpenAIRE

    Vinardell Martínez-Hidalgo, Ma. Pilar

    2014-01-01

    In Europe, the safety evaluation of cosmetics is based on the safety evaluation of each individual ingredient. Article 3 of the Cosmetics Regulation specifies that a cosmetic product made available on the market is to be safe for human health when used normally or under reasonably foreseeable conditions. For substances that cause some concern with respect to human health (e.g. colorants, preservatives, UV-filters), safety is evaluated at the Commission level by a scientific committee, present...

  11. Safety of the Gadolinium-Based Contrast Agents for Magnetic Resonance Imaging, Focusing in Part on Their Accumulation in the Brain and Especially the Dentate Nucleus.

    Science.gov (United States)

    Runge, Val M

    2016-05-01

    The established class of intravenous contrast media for magnetic resonance imaging is the gadolinium chelates, more generally referred to as the gadolinium-based contrast agents (GBCAs). These can be differentiated on the basis of stability in vivo, with safety and tolerability of the GBCAs dependent upon chemical and biologic inertness. This review discusses first the background in terms of development of these agents and safety discussions therein, and second their relative stability based both on in vitro studies and clinical observations before and including the advent of nephrogenic systemic fibrosis. This sets the stage for the subsequent focus of the review, the current knowledge regarding accumulation of gadolinium in the brain and specifically the dentate nucleus after intravenous administration of the GBCAs and differentiation among agents on this basis. The information available to date, from the initial conception of these agents in 1981 to the latest reports concerning safety, demonstrates a significant difference between the macrocyclic and linear chelates. The review concludes with a discussion of the predictable future, which includes, importantly, a reassessment of the use of the linear GBCAs or a subset thereof. PMID:26945278

  12. Evaluation of safety in the transportation of natural uranium hexafluoride

    International Nuclear Information System (INIS)

    A general model developed for the safety of transporting radioactive materials is applied to UF6. Results given concern only the container contents during an accident; harmful consequences to the environment are not considered. It is shown that railroad transport is safer than road transport, particularly with regard to fire. 13 figs., 12 tables

  13. Observing the Safety Precautions Against Blood-Borne Infections by Delivery Agents in Therapeutic and Training Hospitals of Tabriz in 2011-2012

    Directory of Open Access Journals (Sweden)

    Soheila Bani

    2014-01-01

    Full Text Available Objectives: Blood transferred disease is one of the great difficulties for human and it is counted as one of the serious problems of public health. Although health care is valuable, it has some risks such as contacting with various pathogens, especially blood transferred pathogens, so the aim of this study is to observe the safety precautions against blood-borne infections by delivery agents in therapeutic and training hospitals of Tabriz in 2012. Materials and Methods: This study is a descriptive research and all of the participants were the childbirth agents in 3 hospital of Tabriz (Alzahra , Taleghani , 29 Bahman. All of sample size was 100 persons. After obtaining informed consent, the questionnaires which contain demographic information and 24 statements that they were related to observance of safety points against blood transferred infections in childbirth rooms were given to participants to complete. The data were analyzed with SPSS software (Ver. 13. Results: Results showed that the rate of total observance of safety precautions against blood transmitted diseases was good in 54% of delivery agents and in 46% of them was average. Conclusion: Observing safety precautions against blood transmitted diseases needs motivation, effective education and necessary, that all of them should be in priority of health care planning by relevant authorities to reduce contaminated individuals and the costs of their treatment.

  14. Safety Evaluation Report related to the operation of Wolf Creek Generating Station, Unit No. 1 (Docket No. STN 50-482). Supplement No. 6

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (SER) for the application filed by the Kansas Gas and Electric Company, as applicant and agent for the owners, for a license to operate the Wolf Creek Generating Station, Unit 1 (Docket No. STN 50-482). The facility is located in Coffey County, Kansas. This supplement provides recent information regarding resolution of the license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public

  15. Safety evaluation of Phytovagex, a pessary formulation of Nigella sativa, on pregnant rats

    Directory of Open Access Journals (Sweden)

    Reza Salarinia

    2016-01-01

    Full Text Available Objective: The possible toxicity of drugs in pregnancy should be tested before their use in pregnant patients. In the present study, we aimed to evaluate the safety of phytovagex, a pessary formulation of Nigella sativa (N. sativa, which is already in clinical use for vaginal fungal infection. Materials and Methods: The pregnant rats were treated intravaginal with physiological saline (vehicle or phytovagex pessary in the first half of their pregnancy (days 1 to 10 of gestation. Duration of pregnancy and health parameters of the newborns were recorded after parturition. Also, cytotoxicity of N. sativa hydroalcoholic extract was tested against ovary Cho cells.  Results: The phytovagex had no significant effect on the duration of pregnancy, number of newborns, weight of neonates, and percent of stillbirth. No deformity or general behavioral abnormality was observed in neonates monitored for 30 days after birth. N. sativa extract had no significant effect on the viability of ovary cells at the concentrations of 12.5-200 µg/mL. Conclusion: Results of this animal study showed that phytovagex has no overall effect on the duration of pregnancy and health parameters of the newborns. Also, its active agent, N. sativa, does not induce any cytotoxic effect on ovary cells.

  16. Teaching Safety Skills to Children to Prevent Gun Play: An Evaluation of in Situ Training

    Science.gov (United States)

    Miltenberger, Raymond G.; Gatheridge, Brian J.; Satterlund, Melisa; Egemo-Helm, Kristin R.; Johnson, Brigitte M.; Jostad, Candice; Kelso, Pamela; Flessner, Christopher A.

    2005-01-01

    This study evaluated behavioral skills training with added in situ training for teaching safety skills to prevent gun play. Following baseline, each child received two sessions of behavioral skills training and one in situ training session. Additional in situ training sessions were conducted until the child exhibited the safety skills (don't touch…

  17. 21 CFR 570.20 - General principles for evaluating the safety of food additives.

    Science.gov (United States)

    2010-04-01

    ... food additives. 570.20 Section 570.20 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS FOOD ADDITIVES Food Additive Safety § 570.20 General principles for evaluating the safety of food additives. (a) In reaching...

  18. 21 CFR 170.20 - General principles for evaluating the safety of food additives.

    Science.gov (United States)

    2010-04-01

    ... food additives. 170.20 Section 170.20 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) FOOD FOR HUMAN CONSUMPTION (CONTINUED) FOOD ADDITIVES Food Additive Safety § 170.20 General principles for evaluating the safety of food additives. (a) In reaching...

  19. Development of an Evaluation Tool for Online Food Safety Training Programs

    Science.gov (United States)

    Neal, Jack A., Jr.; Murphy, Cheryl A.; Crandall, Philip G.; O'Bryan, Corliss A.; Keifer, Elizabeth; Ricke, Steven C.

    2011-01-01

    The objective of this study was to provide the person in charge and food safety instructors an assessment tool to help characterize, identify strengths and weaknesses, determine the completeness of the knowledge gained by the employee, and evaluate the level of content presentation and usability of current retail food safety training platforms. An…

  20. An Evaluation Methodology Development and Application Process for Severe Accident Safety Issue Resolution

    OpenAIRE

    Martin, Robert P.

    2012-01-01

    A general evaluation methodology development and application process (EMDAP) paradigm is described for the resolution of severe accident safety issues. For the broader objective of complete and comprehensive design validation, severe accident safety issues are resolved by demonstrating comprehensive severe-accident-related engineering through applicable testing programs, process studies demonstrating certain deterministic elements, probabilistic risk assessment, and severe accident management...

  1. Occupational Safety and Health Professionals' Training in Italy: Qualitative Evaluation Using T-LAB

    Science.gov (United States)

    Papaleo, Bruno; Cangiano, Giovanna; Calicchia, Sara

    2013-01-01

    Purpose: The purpose of this paper is to describe the evaluation of a training course on chemicals for occupational safety and health (OSH) professionals. The study aims were to assess the effectiveness of the course; to find out what type of training met these workers' needs best, as their role is vital in the management of safety at work; and to…

  2. Safety evaluation report related to the preliminary design of the Standard Reference System, RESAR-414

    International Nuclear Information System (INIS)

    The safety evaluation for the Westinghouse Standard Reactor includes information on general reactor characteristics; design criteria for systems and components; reactor coolant system; engineered safety systems; instrumentation and controls; electric power systems; auxiliary systems; steam and power conversion system; radioactive waste management; radiation protection; conduct of operations; accident analyses; and quality assurance

  3. Effectiveness evaluation methodology for safety processes to enhance organisational culture in hazardous installations.

    Science.gov (United States)

    Mengolini, A; Debarberis, L

    2008-06-30

    Safety performance indicators are widely collected and used in hazardous installations. The IAEA, OECD and other international organisations have developed approaches that strongly promote deployment of safety performance indicators. These indicators focus mainly on operational performance, but some of them also address organisational and safety culture aspects. However, operators of hazardous installations, in particular those with limited resources and time constraints, often find it difficult to collect the large number of different safety performance indicators. Moreover, they also have difficulties with giving a meaning to the numbers and trends recorded, especially to those that should reflect a positive safety culture. In this light, the aim of this article is to address the need to monitor and assess progress on implementation of a programme to enhance safety and organisational culture. It proposes a specific process-view approach to effectiveness evaluation of organisational and safety culture indicators by means of a multi-level system in which safety processes and staff involvement in defining improvement activities are central. In this way safety becomes fully embedded in staff activities. Key members of personnel become directly involved in identifying and supplying leading indicators relating to their own daily activity and become responsible and accountable for keeping the measurement system alive. Besides use of lagging indicators, particular emphasis is placed on the importance of identifying and selecting leading indicators which can be used to drive safety performance for organisational and safety culture aspects as well. PMID:18241983

  4. Effectiveness evaluation methodology for safety processes to enhance organisational culture in hazardous installations

    International Nuclear Information System (INIS)

    Safety performance indicators are widely collected and used in hazardous installations. The IAEA, OECD and other international organisations have developed approaches that strongly promote deployment of safety performance indicators. These indicators focus mainly on operational performance, but some of them also address organisational and safety culture aspects. However, operators of hazardous installations, in particular those with limited resources and time constraints, often find it difficult to collect the large number of different safety performance indicators. Moreover, they also have difficulties with giving a meaning to the numbers and trends recorded, especially to those that should reflect a positive safety culture. In this light, the aim of this article is to address the need to monitor and assess progress on implementation of a programme to enhance safety and organisational culture. It proposes a specific process-view approach to effectiveness evaluation of organisational and safety culture indicators by means of a multi-level system in which safety processes and staff involvement in defining improvement activities are central. In this way safety becomes fully embedded in staff activities. Key members of personnel become directly involved in identifying and supplying leading indicators relating to their own daily activity and become responsible and accountable for keeping the measurement system alive. Besides use of lagging indicators, particular emphasis is placed on the importance of identifying and selecting leading indicators which can be used to drive safety performance for organisational and safety culture aspects as well

  5. Study and Application of Safety Risk Evaluation Model for CO2 Geological Storage Based on Uncertainty Measure Theory

    OpenAIRE

    Hujun He; Yaning Zhao; Xingke Yang; Yaning Gao; Xu Wu

    2015-01-01

    Analyzing showed that the safety risk evaluation for CO2 geological storage had important significance. Aimed at the characteristics of CO2 geological storage safety risk evaluation, drawing on previous research results, rank and order models for safety risk evaluation of CO2 geological storage were put forward based on information entropy and uncertainty measure theory. In this model, the uncertainty problems in safety risk evaluation of CO2 geological storage were solved by qualitative anal...

  6. Efficacy and safety of second-line agents for treatment of metastatic castration-resistant prostate cancer progressing after docetaxel. A systematic review and meta-analysis

    Directory of Open Access Journals (Sweden)

    Gianpaolo Perletti

    2015-07-01

    Full Text Available Objective: We performed a systematic review of the literature to assess the efficacy and the safety of second-line agents targeting metastatic castration-resistant prostate cancer (mCRPC that has progressed after docetaxel. Pooled-analysis was also performed, to assess the effectiveness of agents targeting the androgen axis via identical mechanisms of action (abiraterone acetate, orteronel. Materials and Methods: We included phase III randomized controlled trials that enrolled patients with mCRPC progressing during or after first-line docetaxel treatment. Trials were identified by electronic database searching. The primary outcome of the review was overall survival. Secondary outcomes were radiographic progression-free survival (rPFS and severe adverse effects (grade 3 or higher. Results: Ten articles met the inclusion criteria for the review. These articles reported the results of five clinical trials, enrolling in total 5047 patients. The experimental interventions tested in these studies were enzalutamide, ipilimumab, abiraterone acetate, orteronel and cabazitaxel. Compared to control cohorts (active drug-treated or placebotreated, the significant overall survival advantages achieved were 4.8 months for enzalutamide (hazard ratio for death vs. placebo: 0.63; 95% CI 0.53 to 0.75, P < 0.0001, 4.6 months for abiraterone (hazard ratio for death vs. placebo: 0.66, 95% CI 0.58 to 0.75, P < 0.0001 and 2.4 months for cabazitaxel (hazard ratio for death vs. mitoxantrone-prednisone: 0.70, 95% CI 0.59 to 0.83, p < 0.0001. Pooled analysis of androgen synthesis inhibitors orteronel and abiraterone resulted in significantly increased overall and progression-free survival for anti-androgen agents, compared to placebo (hazard ratio for death: 0.76, 95% CI 0.67 to 0.87, P < 0.0001; hazard ratio for radiographic progression: 0.7, 95% CI 0.63 to 0.77, P < 0.00001. Androgen synthesis inhibitors induced significant increases in risk ratios for adverse effects

  7. Consideration on rationalization of reactor safety systems. Evaluation of impact to plant safety and operations against facility sharing

    International Nuclear Information System (INIS)

    In the Feasibility Study of JNC, sodium cooled large-scale fast reactor and medium-scale modular reactor are studied as two of promising concepts. Sodium cooled medium-scale modular reactor has disadvantage compared to large-scale reactor that has large-scale effect. To compensate the disadvantage, modular effects are facilitated to improve facility sharing among modules, learning effect and so on. But facility sharing makes the plant system complex and impacts to plant safety and operations are worried. We evaluated the impacts to plant safety and operations by facility sharing in sodium cooled medium-scale modular reactor. We arranged ideas of facility sharing and extracted four ideas which are considered to have big impacts to safety or operations. 1) Sharing of the central control room, 2) Reduction of emergency generators, 3) Adoption of large capacity turbines, 4) Sharing of auxiliary cooling water system. In this study, we evaluated impacts to safety, operability, annual inspection and availability under consideration of the risk for unscheduled shutdown against above four facility sharing plans. Consistency of the facility sharing was confirmed. (author)

  8. Safety margin evaluation concepts for plant Up rates and life extension. Results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP)

    International Nuclear Information System (INIS)

    This presentation summarizes results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP) aimed to develop generalized safety margin concept and means of its quantification for the process of evaluating plant safety in the frame of plant life extension and power up rating activities to be used by OECD member countries. (author)

  9. 76 FR 65734 - Guidance for Industry on Evaluating the Safety of Flood-Affected Food Crops for Human Consumption...

    Science.gov (United States)

    2011-10-24

    ... HUMAN SERVICES Food and Drug Administration Guidance for Industry on Evaluating the Safety of Flood... entitled ``Guidance for Industry: Evaluating the Safety of Flood-Affected Food Crops for Human Consumption... industry entitled ``Evaluating the Safety of Flood-affected Food Crops for Human Consumption''...

  10. EDGE study in Russian Federation: efficacy and safety of vildagliptine in comparison with other oral antidiabetic agents in patients with type 2 diabetes mellitus

    Directory of Open Access Journals (Sweden)

    G R Galstyan

    2013-06-01

    Full Text Available According to international consensus, metformin is acknowledged as a first-line therapeutic agent for type 2 diabetes mellitus (T2DM. However, in most cases this treatment eventually requires intensification by supplementation with other hypoglycemic medications. The aim of the EDGE study (Effective Diabetes control with vildaGliptin and vildagliptin/mEtformin was to assess the efficacy and safety of vildagliptin in comparison with other oral agents in routine management of patients with T2DM that has been poorly controlled by metformin monotherapy.

  11. Evaluation of biological control agents for mosquitoes control in artificial breeding places

    Institute of Scientific and Technical Information of China (English)

    Salim Abadi Yaser; Vatandoost Hassan; Rassi Yavar; Abai Mohammad Reza; Sanei Dehkordi Ali Reza; Paksa Azim

    2010-01-01

    Objective:To evaluate the entomological impact of chlorpyrifos-methyl,Bacillus thuringiensis, andGambusia affinis on mosquitoes control in artificial breeding places.Methods:A Latin square design with 4 replicates was performed in order to evaluate the efficacy of chlorpyrifos-methyl,Bacillus thuringiensis, andGambusia affinis on larva. The larvicide was applied at the dosage of 100 mg a.h/ha,Bacillus thuringiensis at the recommended dosage and 10 fishes per m2 were applied at 1í1 m2 artificial breeding sites. The larval densities for both anopheline and culicine were counted according to larvae /10 dippers prior and 24 h after application.Results:All three control agents are effective for mosquito density reduction, and the difference between the three agents and the control is significant (P<0.05). There is also significant difference among chlorpyrifos-methyl,Bacillus thuringiensis andGambusia affinis.Bacillus thuringiensisexhibited more reduction on mosquito larval density than fish and larvicide (P<0.05).Conclusions:Bacillus thuringiensis in comparison with two other agents is the appropriate method for larviciding in the breeding places. Although long term assessing for biological activities as well as monitoring and mapping of resistance is required.

  12. Pineapple juice as a negative oral contrast agent in magnetic resonance cholangiopancreatography: a preliminary evaluation.

    Science.gov (United States)

    Riordan, R D; Khonsari, M; Jeffries, J; Maskell, G F; Cook, P G

    2004-12-01

    The quality of magnetic resonance cholangiopancreatography (MRCP) images is frequently degraded by high signal from the gastrointestinal tract. The aim of this study is to evaluate pineapple juice (PJ) as an oral negative contrast agent in MRCP. Preliminary in vitro evaluation demonstrated that PJ shortened T(2) relaxation time and hence decreased T(2) signal intensity on a standard MRCP sequence to a similar degree to a commercially available negative contrast agent (ferumoxsil). Electrothermal atomic absorption spectrometry assay demonstrated a high manganese concentration in PJ of 2.76 mg dl(-1), which is likely to be responsible for its T(2) imaging properties. MRCP was subsequently performed in 10 healthy volunteers, before and at 15 min and 30 min following ingestion of 400 ml of PJ. Images were assessed blindly by two Consultant Radiologists using a standard grading technique based on contrast effect (degree of suppression of bowel signal), and image effect (diagnostic quality). There were statistically significant improvements in contrast and image effect between pre and post PJ images. There was particularly significant improvement in visualization of the pancreatic duct, but no significant difference between 15 min and 30 min post PJ images. Visualization of the ampulla, common bile duct, common hepatic and central intrahepatic ducts were also significantly improved at 15 min following PJ. Our results demonstrate that PJ, may be used as an alternative to commercially available negative oral contrast agent in MRCP. PMID:15569640

  13. Analysis on evaluation ability of nonlinear safety assessment model of coal mines based on artificial neural network

    Institute of Scientific and Technical Information of China (English)

    SHI Shi-liang; LIU Hai-bo; LIU Ai-hua

    2004-01-01

    Based on the integration analysis of goods and shortcomings of various methods used in safety assessment of coal mines, combining nonlinear feature of mine safety sub-system, this paper establishes the neural network assessment model of mine safety, analyzes the ability of artificial neural network to evaluate mine safety state, and lays the theoretical foundation of artificial neural network using in the systematic optimization of mine safety assessment and getting reasonable accurate safety assessment result.

  14. Basis of Technical Guideline for FBR Fuel Safety Evaluation in JNES

    International Nuclear Information System (INIS)

    Technical guideline for LMFBR fuel safety evaluation has not yet established in Japan also in the world. The guideline for LMFBR MOX fuel is now being studied by JNES. The draft version of the technical guideline will be provided with the current Monju fuel and will be reviewed in order to list up additional safety issues when the guideline is applied with the LMFBR MOX fuels of Monju up-graded core and of next Japanese demonstration fast reactor. The principal concept of fuel safety design, objectives of safety evaluation, damage modes which correspond to evaluation items, design criteria and design evaluation are briefly reviewed in this paper. The outline of the guideline is also introduced here. (author)

  15. Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

  16. Commissioning nuclear safety evaluation for VVER Type 320

    International Nuclear Information System (INIS)

    Some activities that have been supervised by the State Office for Nuclear Safety during the construction of the Temelin nuclear power plant are described. These include containment prestressing, fresh fuel pool testing, replacement of the Russian instrumentation and control system with a more advanced system, and change in the core configuration to accommodate new design fuel assemblies enabling a better exploitation of the fuel. (M.D.)

  17. Modification of JRR-4 based on safety evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Izumo, Hironobu; Nakajima, Teruo; Funayama, Yoshiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-10-01

    Since the first criticality was achieved on January 28, 1965, JRR-4 has been operated safely until on January 12, 1996. The modification of JRR-4 was planned according to the framework of reduced enrichment on research reactor program. The modification was designed based on the several national safety guides. JRR-4 has some modifications of facilities to satisfy the guides and guides criteria. (author)

  18. The evaluation of research reactor TRIGA MARK II safety

    International Nuclear Information System (INIS)

    In the paper the Probabilistic Safety Analysis (PSA) of a research reactor is described. Five different initiating events were selected and analyzed with the use of event trees. Seven reactor systems were modeled with fault trees. Three groups of radiation releases were introduced - Success, Reactor-Hall, Environment - and their frequencies were estimated. The importance factors of initiating events, human errors and basic events were calculated regarding the consequence groups. (author)

  19. Evaluation of food safety management systems in Serbian dairy industry

    OpenAIRE

    Igor Tomašević; Nada Šmigić; Ilija Đekić; Vlade Zarić; Nikola Tomić; Jelena Miocinovic; Andreja Rajković

    2016-01-01

    This paper reports incentives, costs, difficulties and benefits of food safety management systems implementation in the Serbian dairy industry. The survey involved 27 food business operators with the national milk and dairy market share of 65 %. Almost two thirds of the assessed dairy producers (70.4 %) claimed that they had a fully operational and certified HACCP system in place, while 29.6 % implemented HACCP, but had no third party certification. ISO 22000 was implemented and certified in ...

  20. Using the Tritium Plasma Experiment to evaluate ITER PFC safety

    International Nuclear Information System (INIS)

    The Tritium Plasma Experiment was assembled at Sandia National Laboratories, Livermore to investigate interactions between dense plasmas at low energies and plasma-facing component materials. This apparatus has the unique capability of replicating plasma conditions in a tokamak divertor with particle flux densities of 2 x 1019 ions/cm2 · s and a plasma temperature of about 15 eV using a plasma that includes tritium. With the closure of the Tritium Research Laboratory at Livermore, the experiment was moved to the Tritium Systems Test Assembly facility at Los Alamos National Laboratory. An experimental program has been initiated there using the Tritium Plasma Experiment to examine safety issues related to tritium in plasma-facing components, particularly the ITER divertor. Those issues include tritium retention and release characteristics, tritium permeation rates and transient times to coolant streams, surface modification and erosion by the plasma, the effects of thermal loads and cycling, and particulate production. A considerable lack of data exists in these areas for many of the materials, especially beryllium, being considered for use in ITER. Not only will basic material behavior with respect to safety issues in the divertor environment be examined, but innovative techniques for optimizing performance with respect to tritium safety by material modification and process control will be investigated. Supplementary experiments will be carried out at the Idaho National Engineering Laboratory and Sandia National Laboratory to expand and clarify results obtained on the Tritium Plasma Experiment

  1. Nuclear Power Safety Reporting System. Final evaluation results

    International Nuclear Information System (INIS)

    This document presents the results of a study conducted by the US Nuclear Regulatory Commission of an unobtrusive, voluntary, anonymous third-party managed, nonpunitive human factors data gathering system (the Nuclear power Safety Reporting System - NPSRS) for the nuclear electric power production industry. The data to be gathered by the NPSRS are intended for use in identifying and quantifying the factors that contribute to the occurrence of significant safety incidents involving humans in nuclear power plants. The NPSRS has been designed to encourage participation in the System through guarantees of reporter anonymity provided by a third-party organization that would be responsible for NPSRS management. As additional motivation to reporters for contributing data to the NPSRS, conditional waivers of NRC disciplinary action would be provided to individuals. These conditional waivers of immunity would apply to potential violations of NRC regulations that might be disclosed through reports submitted to the System about inadvertent, noncriminal incidents in nuclear plants. This document summarizes the overall results of the study of the NPSRS concept. In it, a functional description of the NPSRS is presented together with a review and assessment of potential problem areas that might be met if the System were implemented. Conclusions and recommendations resulting from the study are also presented. A companion volume (NUREG/CR-4133, Nuclear Power Safety Reporting System: Implementation and Operational Specifications'') presented in detail the elements, requirements, forms, and procedures for implementing and operating the System. 13 refs

  2. Synthesis and Evaluation of Ciprofloxacin-Nitroxide Conjugates as Anti-Biofilm Agents

    Directory of Open Access Journals (Sweden)

    Anthony D. Verderosa

    2016-06-01

    Full Text Available As bacterial biofilms are often refractory to conventional antimicrobials, the need for alternative and/or novel strategies for the treatment of biofilm related infections has become of paramount importance. Herein, we report the synthesis of novel hybrid molecules comprised of two different hindered nitroxides linked to the piperazinyl secondary amine of ciprofloxacin via a tertiary amine linker achieved utilising reductive amination. The corresponding methoxyamine derivatives were prepared alongside their radical-containing counterparts as controls. Subsequent biological evaluation of the hybrid compounds on preformed P. aeruginosa flow cell biofilms divulged significant dispersal and eradication abilities for ciprofloxacin-nitroxide hybrid compound 10 (up to 95% eradication of mature biofilms at 40 μM. Importantly, these hybrids represent the first dual-action antimicrobial-nitroxide agents, which harness the dispersal properties of the nitroxide moiety to circumvent the well-known resistance of biofilms to treatment with antimicrobial agents.

  3. Design, synthesis, and biological evaluation of anti-EV71 agents.

    Science.gov (United States)

    Li, Peng; Yang, Bailing; Hao, Fei; Wang, Ping; He, Haiying; Huang, Lei; Zhang, Xuan; Zhang, Shengbin; Peng, Xuanjia; Yin, Ke; Hu, Jiao; Chen, Xinsheng; Gu, Zhengxian; Wang, Li; Shen, Liang; Hu, Guoping; Li, Ning; Li, Jian; Chen, Shuhui; Xiao, Wei; Wang, Zhenzhong; Guo, Qingming; Chang, Xiujuan; Zhang, Lanjun; Cai, Qixu; Lin, Tianwei

    2016-07-15

    Enterovirus 71 (EV71) is a major causative agent of hand, foot and mouth disease (HFMD), which can spread its infections to the central nervous and other systems with severe consequences. In this article, design, chemical synthesis, and biological evaluation of various anti-EV71 agents which incorporate Michael acceptors are described. Further SAR study demonstrated that lactone type of Michael acceptor provided a new lead of anti-EV71 drug candidates with high anti-EV71 activity in cell-based assay and enhanced mouse plasma stability. One of the most potent compounds (2K, cell-based anti-EV71 EC50=0.028μM), showed acceptable stability profile towards mouse plasma, which resulted into promising pharmacokinetics in mouse via IP administration. PMID:27234148

  4. Performance Evaluation of an Intelligent Agents Based Model within Irregular WSN Topologies

    Science.gov (United States)

    Ospina, Alberto Piedrahita; Cañola, Alcides Montoya; Carranza, Demetrio Ovalle

    There are many approaches proposed by the scientific community for the implementation and development of Wireless Sensor Networks (WSN). These approaches correspond to different areas of science, such as Electronics, Communications, Computing, Ubiquity, and Quality of Service among others. However, all are subject to the same constraints, because of the nature of WSN devices. The most common constraints of a WSN are the energy consumption, the network nodes organization, the sensor network's task reprogramming, the reliability in the data transmission, the resource optimization (memory and processing), etc. In the Artificial Intelligence Area is has proposed an Distributed System Approach with Mobile Intelligent Agents. An Integration Model of Mobile Intelligent Agents within Wireless Sensor Network solves some of the constraints presented above on WSŃs topologies. However, the model only was tested on the square topologies. In this way, the aim of this paper is to evaluate the performance of this model in irregular topologies.

  5. Evaluation of the food safety training for food handlers in restaurant operations

    Science.gov (United States)

    Park, Sung-Hee; Kwak, Tong-Kyung

    2010-01-01

    This study examined the extent of improvement of food safety knowledge and practices of employee through food safety training. Employee knowledge and practice for food safety were evaluated before and after the food safety training program. The training program and questionnaires for evaluating employee knowledge and practices concerning food safety, and a checklist for determining food safety performance of restaurants were developed. Data were analyzed using the SPSS program. Twelve restaurants participated in this study. We split them into two groups: the intervention group with training, and the control group without food safety training. Employee knowledge of the intervention group also showed a significant improvement in their score, increasing from 49.3 before the training to 66.6 after training. But in terms of employee practices and the sanitation performance, there were no significant increases after the training. From these results, we recommended that the more job-specific and hand-on training materials for restaurant employees should be developed and more continuous implementation of the food safety training and integration of employee appraisal program with the outcome of safety training were needed. PMID:20198210

  6. Development, evaluation, and implementation of safety measures to prevent marine accidents

    OpenAIRE

    Shapiro, Stephen Mark

    1991-01-01

    Methodologies to determine, evaluate, and implement prospective measures for preventing marine collisions and groundings are presented. The use of cost-benefit analysis to evaluate prospective safety measures is emphasized. Prospective safety measures are represented as changes to variables that relate to the life-cycle of an oil tanker. Most of these variables, such as crew size and training, are associated with the operational phase. A systems engineering approac...

  7. Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks

    Energy Technology Data Exchange (ETDEWEB)

    ROGERS, C.A.

    2000-02-17

    This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

  8. Criticality Safety Evaluation of Hanford Site High-Level Waste Storage Tanks

    International Nuclear Information System (INIS)

    This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions

  9. Evaluation of construction safety in DOE course taught in Livermore, California, August 17--August 20, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Handwerk, E.C.

    1992-12-01

    This report summarizes trainee evaluations for the Safety and Health Training Section course, Construction Safety in DOE'', which was conducted on August 17--20 for the San Francisco DOE Office, and taught in Livermore, California. Section 1.1 and 1.2 of this report summarize the quantitative course evaluations that trainees provided upon completion of the course. Appendix A provides a transcript of the trainees' written comments.

  10. Evaluation of construction safety in DOE course taught in Livermore, California, August 17--August 20, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Handwerk, E.C.

    1992-12-01

    This report summarizes trainee evaluations for the Safety and Health Training Section course, ``Construction Safety in DOE``, which was conducted on August 17--20 for the San Francisco DOE Office, and taught in Livermore, California. Section 1.1 and 1.2 of this report summarize the quantitative course evaluations that trainees provided upon completion of the course. Appendix A provides a transcript of the trainees` written comments.

  11. Study on Evaluation Models of Highway Safety Based on Catastrophe Theory

    OpenAIRE

    Hezheng Bi; Linjun Lu; Jian Lu; Chen Wang

    2014-01-01

    Evaluating safety performance of first-class highways in China is important due to their high mortality rates. Traditional models for statistical crash prediction and traffic conflict techniques require long periods of data collection which is time-consuming and labor-intensive. This paper introduces a safety evaluation method based on catastrophe theory for highways in China. The method firstly divides the highway into multiple road sections and uses video-based road detection (VRD) system t...

  12. Safety Evaluation Report related to the operation of River Bend Station (Docket No. 50-458)

    International Nuclear Information System (INIS)

    Supplement No. 1 to the Safety Evaluation Report on the application filed by Gulf States Utilities Company as applicant and for itself and Cajun Electric Power Cooperative, as owners, for a license to operate River Bend Station has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  13. Thirty years of preclinical safety evaluation of biopharmaceuticals: did scientific progress lead to appropriate regulatory guidance?

    OpenAIRE

    Kooijman, M.; Van Meer, P.J.K.; Moors, E.H.M.; Schellekens, H

    2012-01-01

    Introduction: The first biopharmaceuticals were developed 30 years ago. Biopharmaceuticals differ significantly from small molecule therapeutics (SMTs). Because of such differences, it was expected that classical preclinical safety evaluation procedures applied to SMTs would not predict the adverse effects of biopharmaceuticals. Therefore, until sufficient experience was gained, the preclinical safety evaluation of biopharmaceuticals was carried out on a case-by-case basis. 30 years of experi...

  14. An approach using multi-factor combination to evaluate high rocky slope safety

    OpenAIRE

    Su, Huaizhi; Meng YANG; Wen, Zhiping

    2016-01-01

    A high rocky slope is an open complex giant system for which there is contradiction among different influencing factors and coexistence of qualitative and quantitative information. This study presents a comprehensive intelligent evaluation method of high rocky slope safety through an integrated analytic hierarchy process, extension matter element model and entropy weight to assess the safety behavior of the high rocky slope. The proposed intelligent evaluation integrates subjec...

  15. Study of system safety evaluation on LTO of national project. Thermal fatigue evaluation of piping systems

    International Nuclear Information System (INIS)

    Nuclear piping has various kinds of thermal fatigue failure modes. Main causes of thermal loads are structural responses to fluid temperature changes during plant operation. These phenomena have complex mechanisms and so many patterns, that their problems still occur even though well-known issues. To prevent thermal fatigue due to above thermal loads, the JSME guideline is adopted. Both thermal load and fatigue failure mechanism have been investigated and summarized into the knowledgebase. Numerical simulation methods for thermal fatigue evaluation were studied to replace structural tests. Theses knowledge was utilized to validate and justify the JSME guideline. Furthermore, new studies have been launched to apply above knowledge to enhance plant system safety. (author)

  16. Evaluation of Land Safety Degree of the Tourist Area Based on the Land Comprehensive Bearing Capacity

    Directory of Open Access Journals (Sweden)

    Sun Chao

    2015-09-01

    Full Text Available The regional land safety evaluation indicator system is built based on the land comprehensive bearing capacity in the study and the primary and secondary relationship of the land safety obstacle factors of Mengshan tourist area and influence degree of various obstacle factors on land safety are determined, so as to provide reference for sustainable utilization of land in Mengshan tourist area. The results indicate that: (i The land comprehensive bearing capacity of Mengshan tourist area is at the safety state. Where, the social bearing capacity is at the weak safety state, which is the most critical factor influencing the land bearing capacity of Mengshan tourist area. (ii The traveling and living ratio, the output values of the secondary industry and the tertiary industry of the unit construction land and the land utilization intensity are the key factors influencing the regional safety level.

  17. Preparation and evaluation of a radiogallium complex-conjugated bisphosphonate as a bone scintigraphy agent

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Kazuma, E-mail: kogawa@p.kanazawa-u.ac.jp [Graduate School of Natural Science and Technology, Kanazawa University, Kanazawa 920-1192 (Japan); Takai, Kenichiro; Kanbara, Hiroya; Kiwada, Tatsuto [Graduate School of Natural Science and Technology, Kanazawa University, Kanazawa 920-1192 (Japan); Kitamura, Yoji; Shiba, Kazuhiro [Advanced Science Research Center, Kanazawa University, Kanazawa 920-8640 (Japan); Odani, Akira [Graduate School of Natural Science and Technology, Kanazawa University, Kanazawa 920-1192 (Japan)

    2011-07-15

    Introduction: {sup 68}Ga is a radionuclide of great interest as a positron emitter for positron emission tomography (PET). To develop a new bone-imaging agent with radiogallium, 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (DOTA) was chosen as a chelating site and Ga-DOTA complex-conjugated bisphosphonate, which has a high affinity for bone, was prepared and evaluated. Although we are interested in developing {sup 68}Ga-labeled bone imaging agents for PET, in these initial studies {sup 67}Ga was used because of its longer half-life. Methods: DOTA-conjugated bisphosphonate (DOTA-Bn-SCN-HBP) was synthesized by conjugation of 2-(4-isothiocyanatebenzyl)-1,4,7,10-tetraazacyclododecane-1,4,7, 10-tetraacetic acid to 4-amino-1-hydroxybutylidene-1,1-bisphosphonate (alendronate). {sup 67}Ga-DOTA-Bn-SCN-HBP was prepared by coordination with {sup 67}Ga, and its in vitro and in vivo evaluations were performed. Results: {sup 67}Ga-DOTA-Bn-SCN-HBP was prepared with a radiochemical purity of over 95% without purification. {sup 67}Ga-DOTA-Bn-SCN-HBP had great affinity for hydroxyapatite in binding assay. In biodistribution experiments, {sup 67}Ga-DOTA-Bn-SCN-HBP accumulated in bone rapidly but was hardly observed in tissues other than bone. Pretreatment of an excess amount of alendronate inhibited the bone accumulation of {sup 67}Ga-DOTA-Bn-SCN-HBP. Conclusions: {sup 67}Ga-DOTA-Bn-SCN-HBP showed ideal biodistribution characteristics as a bone-imaging agent. These findings should provide useful information on the drug design of bone imaging agents for PET with {sup 68}Ga.

  18. Basis of technical guideline for FBR fuel safety evaluation in JNES

    International Nuclear Information System (INIS)

    The guideline for safety evaluation of LMFR MOX fuel is now being studied. The draft version of the technical guideline will be completed with the current Monju fuel and will be reviewed in order to list up additional safety issues when the guideline is applied with the LMFR MOX fuels of Monju up-graded core and of next Japanese demonstration fast reactor. It is considered that a lot of items shall be evaluated in order to confirm fuel safety during normal, transient and accident conditions. Fuel safety means to maintain its functions and to keep its integrity. These items are identified in this paper with three major functions, which are essentially requested for reactor safety, and the major functions are reactor shutdown, core cooling and containment of radioactive materials. Total of 13 items for LMFR fuel safety evaluation are identified and total of 17 items for LWR fuel safety are also identified. Safety Review Plan, which is published by United State Nuclear Regulatory Commission (US-NRC), is referred in order to list up the items for LWR fuel safety evaluation. The items for both LMFR fuel and LWR fuel safety evaluations are compared in Table 1 together with specific materials and irradiation level. The safety items which are different between LMFR and LWR are shadowed by yellow. As shown in this table, the number of the items for LMFR fuel safety evaluation is less than that for LWR one. It might be considered that safety of LMFR fuel can be more easily evaluated as compared with safety evaluation of LWR fuel, especially concerning the functions of core cooling and containment. This means that irradiation behavior of LMFR fuel during irradiation might be simpler than that of LWR fuel since coolant pressure is low and boiling temperature of coolant is much higher than temperature at normal operation and the fuel behavior is mild under the transient over power (TOP) and loss of flow (LOF) conditions for LMFR. It might be concluded that the items to be

  19. Development of an Integrity Evaluation Method for Safety-Critical Components of NPPs Using MFM

    International Nuclear Information System (INIS)

    The maintenance strategy of NPPs has been changed from time-based maintenance to condition-based maintenance. In this study, the safety-critical components included in safety-critical system can be usually divided into motor-driven valves and pumps. Among the various pumps included in safety-critical component, high pressure safety injection pump was selected and the failure modes of safety-critical components are analyzed to develop the monitoring technology. Also, this study developed the integrity evaluation method using MFM. This is a methodology in means-end and part-whole way, for automatic real time fault diagnosis of power plant process failure. This study shows MFM based fault diagnosis approach for the HPSI pump. Therefore, the possibility of using MFM for the integrity evaluation for HPSI pump in confirmed through this study

  20. Preliminary safety evaluation (PSE) for Sodium Storage Facility at the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    This evaluation was performed for the Sodium Storage Facility (SSF) which will be constructed at the Fast Flux Test Facility (FFTF) in the area adjacent to the South and West Dump Heat Exchanger (DHX) pits. The purpose of the facility is to allow unloading the sodium from the FFTF plant tanks and piping. The significant conclusion of this Preliminary Safety Evaluation (PSE) is that the only Safety Class 2 components are the four sodium storage tanks and their foundations. The building, because of its imminent risk to the tanks under an earthquake or high winds, will be Safety Class 3/2, which means the building has a Safety Class 3 function with the Safety Class 2 loads of seismic and wind factored into the design

  1. A New Method for the Evaluation of Vaccine Safety Based on Comprehensive Gene Expression Analysis

    Directory of Open Access Journals (Sweden)

    Haruka Momose

    2010-01-01

    Full Text Available For the past 50 years, quality control and safety tests have been used to evaluate vaccine safety. However, conventional animal safety tests need to be improved in several aspects. For example, the number of test animals used needs to be reduced and the test period shortened. It is, therefore, necessary to develop a new vaccine evaluation system. In this review, we show that gene expression patterns are well correlated to biological responses in vaccinated rats. Our findings and methods using experimental biology and genome science provide an important means of assessment for vaccine toxicity.

  2. Use of the event tree method for evaluate the safety of radioactive facilities

    International Nuclear Information System (INIS)

    The work shows the validity of the use of Trees of Events like a quantitative method appropriate to carry out evaluations of radiological safety. Its were took like base the evaluations of safety of five Radiotherapy Departments, carried out in the mark of the process of authorization of these facilities. The risk values were obtained by means of the combination of the probabilities of occurrence of the events with its consequences. The use of the method allowed to suggest improvements to the existent safety systems, as well as to confirm that the current regulator requirements for this type of facilities to lead to practices with acceptable risk levels. (Author)

  3. A Web-based Alternative Non-animal Method Database for Safety Cosmetic Evaluations

    Science.gov (United States)

    Kim, Seung Won; Kim, Bae-Hwan

    2016-01-01

    Animal testing was used traditionally in the cosmetics industry to confirm product safety, but has begun to be banned; alternative methods to replace animal experiments are either in development, or are being validated, worldwide. Research data related to test substances are critical for developing novel alternative tests. Moreover, safety information on cosmetic materials has neither been collected in a database nor shared among researchers. Therefore, it is imperative to build and share a database of safety information on toxicological mechanisms and pathways collected through in vivo, in vitro, and in silico methods. We developed the CAMSEC database (named after the research team; the Consortium of Alternative Methods for Safety Evaluation of Cosmetics) to fulfill this purpose. On the same website, our aim is to provide updates on current alternative research methods in Korea. The database will not be used directly to conduct safety evaluations, but researchers or regulatory individuals can use it to facilitate their work in formulating safety evaluations for cosmetic materials. We hope this database will help establish new alternative research methods to conduct efficient safety evaluations of cosmetic materials. PMID:27437094

  4. A Web-based Alternative Non-animal Method Database for Safety Cosmetic Evaluations.

    Science.gov (United States)

    Kim, Seung Won; Kim, Bae-Hwan

    2016-07-01

    Animal testing was used traditionally in the cosmetics industry to confirm product safety, but has begun to be banned; alternative methods to replace animal experiments are either in development, or are being validated, worldwide. Research data related to test substances are critical for developing novel alternative tests. Moreover, safety information on cosmetic materials has neither been collected in a database nor shared among researchers. Therefore, it is imperative to build and share a database of safety information on toxicological mechanisms and pathways collected through in vivo, in vitro, and in silico methods. We developed the CAMSEC database (named after the research team; the Consortium of Alternative Methods for Safety Evaluation of Cosmetics) to fulfill this purpose. On the same website, our aim is to provide updates on current alternative research methods in Korea. The database will not be used directly to conduct safety evaluations, but researchers or regulatory individuals can use it to facilitate their work in formulating safety evaluations for cosmetic materials. We hope this database will help establish new alternative research methods to conduct efficient safety evaluations of cosmetic materials. PMID:27437094

  5. Safety evaluation by use of living PSA and safety indicators - Current status and future development of models and tools within the Nordic project safety evaluation, NKS/SIK-1

    International Nuclear Information System (INIS)

    The paper presents the preproject results and the early phase of the Nordic research project ''Safety Evaluation, NKS/SIK-1'' (1990-93). The subjects discussed are mainly problem investigation and identification of development areas for the living PSA part of the project. To make proper safety related decisions and evaluations, the development of the plant state should be carefully monitored and evaluated. The SIK-1 project is intended to define and demonstrate the practical use of living PSA and operational safety indicators for safety evaluation and for the identification of effective improvements in operational safety. In our view, a risk monitoring system, tailored and implemented for plant specific use by its user organizations, can monitor and evaluate the plant state more efficiently, and undesired events can be prevented. The overall status of PSA and the experience gained in performing and utilizing PSA studies are quite similar among all utilities in Sweden and Finland. A natural step is now to pass towards a living use of present Level 1 studies at the plants. A basic PSA model intended for living PSA purposes has to be modified and enhanced in several areas. With data and tool improvements it is further necessary to reach a state where all capabilities of a living PSA are fully explored and utilized. Collection and analysis of relevant operational experience and development of systematic methods for the early identification of degrading developments and deficiencies is considered to be essential for safety. (author). 13 refs, 1 fig., 2 tabs

  6. Criticality safety evaluation for the direct disposal of used nuclear fuel. Preparation of data for burnup credit evaluation (Contract research)

    International Nuclear Information System (INIS)

    In the direct disposal of used nuclear fuel (UNF), criticality safety evaluation is one of the important issues since UNF contains some amount of fissile material. In the conventional criticality safety evaluation of UNF where the fresh fuel composition is conservatively assumed, neutron multiplication factor is becoming overestimated as the fuel enrichment increases. The recent development of higher-enrichment fuel has therefore enhanced the benefit of the application of burnup credit. When applying the burnup credit to the criticality safety analysis of the disposed fuel system, the safe-side estimation of the reactivity is required taking into account the factors which affect the neutron multiplication factor of the burnt fuel system such as the nuclide composition uncertainties. In this report, the effects of the several parameters on the reactivity of disposal canister model were evaluated for used PWR fuel. The parameters are relevant to the uncertainties of depletion calculation code, irradiation history, and axial and horizontal burnup distribution, which are known to be important effect in the criticality safety evaluation adopting burnup credit. The latest data or methodology was adopted in this evaluation, based on the various latest studies. The appropriate margin of neutron multiplication factor in the criticality safety evaluation for UNF can be determined by adopting the methodology described in the present study. (author)

  7. Evaluation of the safety and tolerability profile of Sativex: is it reassuring enough?

    Science.gov (United States)

    Wade, Derick

    2012-04-01

    The adoption of new drug therapies involves an assessment of risk:benefit based upon the best clinical evidence, including clinical trials but also everyday clinical practice data collection. However, in the case of Sativex, a cannabinoid medicine containing the two main active ingredients of cannabis, δ-9-tetrahydrocannabinol and cannabidiol, the picture is somewhat clouded by preconceived views regarding the world's most widely used illicit drug, herbal cannabis. In this review, I aim to look beyond these preconceptions and evaluate the body of published data concerning this medicine currently approved in different countries for the management of one of the most frequent and disabling symptoms associated with multiple sclerosis, spasticity. In particular, data relevant to areas of concern such as tolerability, safety, psychoactivity, effects on withdrawal (including possible drug tolerance) and finally the potential for abuse/dependence are evaluated. Balancing these risk factors, the main positive clinical data published over the years by the Oxford Centre for Enablement, following on from the first pilot study in 2004, are presented. Based upon our experience, the benefits that are seen initially with Sativex when treating multiple sclerosis spasticity patients are generally maintained during long-term treatment. Furthermore, following withdrawal of Sativex, symptoms often return, but, beyond this, sudden cessation is generally safe with no evidence of physiological or psychological dependence. Dose escalation has not usually been observed in clinical trials or clinical practice after the first titration weeks. Adverse effects occur relatively frequently, but they are usually mild to moderate in intensity and rarely require drug discontinuation. Overall, Sativex appears to be well-tolerated and a useful addition for patients who have failed treatment with traditional antispastic agents. PMID:22509986

  8. Image quality and safety in pediatric urography using an ionic and a non-ionic iodinated contrast agent

    International Nuclear Information System (INIS)

    The safety and diagnostic efficacy of the new non-ionic, monomeric contrast medium iopentol (Imagopaque) were evaluated and compared with those of the ionic medium metrizoate (Isopaque), in urography in children in a randomized, double-blind, parallel study. The trial comprised 59 children aged from 3 months to 8 years; children with predefined risk factors were not included. The difference in attenuation between the renal and perirenal tissue, assessed from film density measurements, was chosen as the main variable. Diagnostic efficacy was also evaluated subjectively from demarcation of the kidney and the pelvic structures. There was no statistically significant difference between the groups in the diagnostic efficacy. Serious adverse events did not occur in either group. Mild to moderate, transient adverse events were significantly less frequent in the iopentol group than in the metrizoate group, but in no case was medical treatment required. There were no changes or trends toward changes of clinical importance in either group, in serum chemistry variables measured in blood samples taken 2 min after injection of contrast medium compared to baseline values. (orig.)

  9. Evaluation of life safety risks related to severe flooding

    OpenAIRE

    Ehsan, Saqib

    2009-01-01

    The flooding risk has always been considered to be very important for the risk safety management of dams. The extreme flooding downstream of a dam could be either due to dam failure or sometimes it can occur without failure. In both cases, it poses serious risks to people and property downstream of the dam. In this study, the risk assessment for the Jhelum river valley downstream of Mangla dam has been carried out. Mangla dam is one of the large earth and rock-fill dams in the world. The hei...

  10. Study on development of education model and its evaluation system for radiation safety

    CERN Document Server

    Seo, K W; Nam, Y M

    2002-01-01

    As one of the detailed action strategy of multi object preparedness for strengthening of radiation safety management by MOST, this project was performed, in order to promote the safety culture for user and radiation worker through effective education program. For the prevention of radiological accident and effective implementation of radiation safety education and training, this project has been carried out the development of education model and its evaluation system on radiation safety. In the development of new education model, education course was classified; new and old radiation worker, temporary worker, lecturer and manager. The education model includes the contents of expanding the education opportunity and workplace training. In the development of evaluation system, the recognition criteria for commission-education institute and inside-education institute which should establish by law were suggested for evaluation program. The recognition criteria contains classification, student, method, facilities, ...

  11. Food Safety Evaluation Based on Near Infrared Spectroscopy and Imaging: A Review.

    Science.gov (United States)

    Fu, Xiaping; Ying, Yibin

    2016-08-17

    In recent years, due to the increasing consciousness of food safety and human health, much progress has been made in developing rapid and nondestructive techniques for the evaluation of food hazards, food authentication, and traceability. Near infrared (NIR) spectroscopy and imaging techniques have gained wide acceptance in many fields because of their advantages over other analytical techniques. Following a brief introduction of NIR spectroscopy and imaging basics, this review mainly focuses on recent NIR spectroscopy and imaging applications for food safety evaluation, including (1) chemical hazards detection; (2) microbiological hazards detection; (3) physical hazards detection; (4) new technology-induced food safety concerns; and (5) food traceability. The review shows NIR spectroscopy and imaging to be effective tools that will play indispensable roles for food safety evaluation. In addition, on-line/real-time applications of these techniques promise to be a huge growth field in the near future. PMID:24972267

  12. High Speed Railway Environment Safety Evaluation Based on Measurement Attribute Recognition Model

    Directory of Open Access Journals (Sweden)

    Qizhou Hu

    2014-01-01

    Full Text Available In order to rationally evaluate the high speed railway operation safety level, the environmental safety evaluation index system of high speed railway should be well established by means of analyzing the impact mechanism of severe weather such as raining, thundering, lightning, earthquake, winding, and snowing. In addition to that, the attribute recognition will be identified to determine the similarity between samples and their corresponding attribute classes on the multidimensional space, which is on the basis of the Mahalanobis distance measurement function in terms of Mahalanobis distance with the characteristics of noncorrelation and nondimensionless influence. On top of the assumption, the high speed railway of China environment safety situation will be well elaborated by the suggested methods. The results from the detailed analysis show that the evaluation is basically matched up with the actual situation and could lay a scientific foundation for the high speed railway operation safety.

  13. A proposal to Asian countries with operating research reactors for making nuclear criticality safety benchmark evaluations

    International Nuclear Information System (INIS)

    The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization for Economic Cooperation and Development-Nuclear Energy Agency (OECD-NEA). 'International Handbook of Criticality Safety Benchmark Experiments' was prepared and is updated yearly by the working group of the project. This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear criticality facilities around the world. However, the handbook lacks criticality data of 20 wt%-enriched uranium fuel. The author proposes to make benchmark specifications derived from modern research reactors in Asia. Future evaluations of these reactors will facilitate to fill the 'enrichment gap'. (author)

  14. Safety Evaluation of UCFR-1000 MWe with MATRA-LMR

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Han; Kang, Sa Rah; Bang, In Cheol [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2012-05-15

    Ultra-long Cycle Fast Reactor (UCFR) is the long-life nuclear reactor without refueling. The concept of UCFR is based on the breed and burn system. The shapes of neutron flux and power density remain constant but they move their position every moment. Sekimoto et al. proposed the CANDLE reactor, which is the basic concept of UCFR. Like CANDLE reactor, Traveling Wave Reactor (TWR) was also introduced as a concept of new reactor. Tak et al. proposed the preliminary concept of UCFR which can produce 1000 MWe. The fuel rod is composed of U-10Zr, the cladding material is HT9, and the coolant is sodium. MATRA-LMR (Multichannel Analyzer for Transient and steady-state in Rod Array for Liquid Metal Reactor) was developed as a subchannel analysis code to calculate the thermal-hydraulic characteristic of liquid metal reactors such as fuel, cladding, and coolant temperatures. In this study, with MATRA-LMR code, the major properties of UCFR-1000 MWe are calculated and compared with KALIMER-600 MWe. Also, the safety margin of UCFR-1000 MWe is analyzed using safety regulation table

  15. Safety Evaluation of UCFR-1000 MWe with MATRA-LMR

    International Nuclear Information System (INIS)

    Ultra-long Cycle Fast Reactor (UCFR) is the long-life nuclear reactor without refueling. The concept of UCFR is based on the breed and burn system. The shapes of neutron flux and power density remain constant but they move their position every moment. Sekimoto et al. proposed the CANDLE reactor, which is the basic concept of UCFR. Like CANDLE reactor, Traveling Wave Reactor (TWR) was also introduced as a concept of new reactor. Tak et al. proposed the preliminary concept of UCFR which can produce 1000 MWe. The fuel rod is composed of U-10Zr, the cladding material is HT9, and the coolant is sodium. MATRA-LMR (Multichannel Analyzer for Transient and steady-state in Rod Array for Liquid Metal Reactor) was developed as a subchannel analysis code to calculate the thermal-hydraulic characteristic of liquid metal reactors such as fuel, cladding, and coolant temperatures. In this study, with MATRA-LMR code, the major properties of UCFR-1000 MWe are calculated and compared with KALIMER-600 MWe. Also, the safety margin of UCFR-1000 MWe is analyzed using safety regulation table

  16. Cytotoxicity evaluation of self-etching dentine bonding agents in a cell culture perfusion condition

    OpenAIRE

    Korsuwannawong, Suwanna; Srichan, Ratchaporn; Vajrabhaya, La-Ongthong

    2012-01-01

    Objective: The aim of this study was to evaluate the cytotoxicity of three dentine bonding agents (G-Bond, Clearfil S3 Bond and Clearfil SE Bond X) in cell-culture perfusion. Methods: In this experiment, 8×104 TCPC SV40 cells (bovine-pulp-derived cells transfected with simian virus 40 large T-antigen) in MEM-alpha media, 20%FCS were seeded on mesh in a 6-well plate and incubated at 37 °C with 5% CO2. After 2 days, the mesh inserts were transferred to a 24-well plate and incubated in MEM-alpha...

  17. Synthesis and preliminary evaluation of N-acylhydrazone compounds as antibacterial and antifungal agents

    International Nuclear Information System (INIS)

    We describe the synthesis and evaluation of N-acylhydrazone compounds bearing different electron-donating groups in one of its aromatic rings, obtained using a four-step synthetic route. IC50 values against pathogenic fungi and bacteria were determined by serial microdilution. Compounds showed low activity against Staphylococcus aureus, Escherichia coli and Pseudomonas aeruginosa. By contrast, a derivative with a meta-oriented electron-donating group showed significant activity (IC50) against Candida albicans (17 μM), C. krusei (34 μM) and C. tropicalis (17 μM). Results suggest this is a promising lead-compound for synthesis of potent antifungal agents. (author)

  18. Synthesis, biological evaluation and SAR studies of benzimidazole derivatives as H1-antihistamine agents

    Institute of Scientific and Technical Information of China (English)

    Xiao Jian Wang; Mei Yang Xi; Ji Hua Fu; Fu Rong Zhang; Gui Fang Cheng; Da Li Yin; Qi Dong You

    2012-01-01

    A series of benzimidazole derivatives have been designed,synthesized and evaluated for H1 antihtistamine activity.Six compounds have showed potent antihistamine H1 activity.The primary SAR analysis indicated that benzyl or benzylidinyl substituted on the exo-nitrogen atom and C2 of the benzimidazole were significant.Further experiments indicated that compound 17d displayed excellent activity to reduce mast cell degranulation,moderate anti-PAF activity and decreased potency on hERG compared to astermizole.Hence compound 17d could serve as anti-altergic agent for further development.

  19. Development of polypropylene/wood flour ecocomposites. Evaluation of silane as coupling agent

    Science.gov (United States)

    Bouza, R.; Barral, L.; Abad, M. J.; Montero, B.

    2010-06-01

    The effects of Pinus Sylvestris wood flour as filler in polypropylene matrix was evaluated. The mechanical properties and the morphology of different wood flour/polypropylene composites (WPC) were studied. The composites materials were prepared with several amounts of wood flour from 10 to 30% wt. Mechanical properties show that the wood flour incorporation increases the rigidity of the composites. Morphological analysis indicates that agglomerates are formed, with amounts exceeding 30% of wood flour. For the silane—treated composites, the dispersion of the filler into the polypropylene (PP) matrix improved. Shore D hardness of the composites is decreased with the addition of the coupling agent.

  20. Synthesis, analysis and biological evaluation of novel indolquinonecryptolepine analogues as potential anti-tumour agents.

    Science.gov (United States)

    Le Gresley, A; Gudivaka, V; Carrington, S; Sinclair, A; Brown, J E

    2016-03-21

    A small library of cryptolepine analogues were synthesised incorporating halogens and/or nitrogen containing side chains to optimise their interaction with the sugar-phosphate backbone of DNA to give improved binding, interfering with topoisomerase II hence enhancing cytotoxicity. Cell viability, DNA binding and Topoisomerase II inhibition is discussed for these compounds. Fluorescence microscopy was used to investigate the uptake of the synthesised cryptolepines into the nucleus. We report the synthesis and anti-cancer biological evaluation of nine novel cryptolepine analogues, which have greater cytotoxicity than the parent compound and are important lead compounds in the development of novel potent and selective indoloquinone anti-neoplastic agents. PMID:26893255

  1. Discovery of potent nitrotriazole-based antitrypanosomal agents: In vitro and in vivo evaluation.

    Science.gov (United States)

    Papadopoulou, Maria V; Bloomer, William D; Rosenzweig, Howard S; O'Shea, Ivan P; Wilkinson, Shane R; Kaiser, Marcel; Chatelain, Eric; Ioset, Jean-Robert

    2015-10-01

    3-Nitro-1H-1,2,4-triazole- and 2-nitro-1H-imidazole-based amides with an aryloxy-phenyl core were synthesized and evaluated as antitrypanosomal agents. All 3-nitrotriazole-based derivatives were extremely potent anti-Trypanosoma cruzi agents at sub nM concentrations and exhibited a high degree of selectivity for the parasite. The 2-nitroimidazole analogs were only moderately active against T. cruzi amastigotes and exhibited low selectivity. Both types of compound were active against Leishmania donovani axenic amastigotes with excellent selectivity for the parasite, whereas three 2-nitroimidazole-based analogs were also moderately active against infected macrophages. However, no compound demonstrated selective activity against Trypanosoma brucei rhodesiense. The most potent in vitro anti-T. cruzi compounds were tested in an acute murine model and reduced the parasites to an undetectable level after five days of treatment at 13 mg/kg/day. Such compounds are potential inhibitors of T. cruzi CYP51 and, being excellent substrates for the type I nitroreductase (NTR) which is specific to trypanosomatids, work as prodrugs and constitute a new generation of effective and more affordable antitrypanosomal agents. PMID:26344593

  2. Quantitative Evaluation of Contamination on Dental Zirconia Ceramic by Silicone Disclosing Agents after Different Cleaning Procedures

    Directory of Open Access Journals (Sweden)

    Sebastian Wille

    2015-05-01

    Full Text Available The aim of this study was to evaluate the effectiveness of cleaning procedures for air-abraded zirconia after contamination with two silicone disclosing agents. Air-abraded zirconia ceramic specimens (IPS e.max ZirCAD were contaminated with either GC Fit Checker white or GC Fit Checker II. Untreated zirconia specimens were used as control. Afterwards the surfaces were cleaned either with waterspray or ultrasonically in 99% isopropanol or using a newly developed cleaning paste (Ivoclean. After cleaning X-ray photoelectron spectroscopy (XPS was performed and the relative peak intensities of Zr, C and Si were used for a qualitative comparison of the residuals. There was no significant difference between the two different silicone disclosing agents. An additional cleaning step with isopropanol led to a significantly lower amount of residuals on the surface, but an additional cleaning process with Ivoclean did not reduce the amount of carbon residuals in comparison to the isopropanol cleaning. Just the silicone amount on the surface was reduced. None of the investigated cleaning processes removed all residuals from the contaminated surface. Standard cleaning processes do not remove all residuals of the silicone disclosing agent from the surface. This may lead to a failure of the resin-ceramic bonding.

  3. Comparison of evaluation guidelines for life-safety seismic hazards

    International Nuclear Information System (INIS)

    The guidelines presented in Design Evaluation guidelines for Department of Energy Facilities Subjected to natural Phenomena Hazards (UCRL 15910 Draft; May 1989) include evaluation criteria for existing Department of Energy buildings subjected to earthquakes. These criteria were developed at the Lawrence Livermore National Laboratory for use in both the seismic design of new structures and the evaluation of existing structures. ATC-14: Evaluating The Seismic Resistance of Existing Buildings developed by the Applied Technology Council, consists of guidelines and criteria for identifying the buildings or building components that present unacceptable risk to human lives. This paper compares and contrasts the two evaluation guidelines for existing buildings using a prototype building as an example. The prototype building is a seven story, concrete shear wall building assuming a General Use Occupancy

  4. The role of the regulator in promoting and evaluating safety culture. Operating experience feedback programme approach

    International Nuclear Information System (INIS)

    Promoting and Evaluating Safety Culture (S.C.) in Operating Organizations must be one of the main Nuclear Regulator goals to achieve. This can be possible only if each and every one of the regulatory activities inherently involves S.C. It can be seen throughout attitudes, values, uses and practices in both individuals and the whole regulatory organization. One among all the regulatory tools commonly used by regulators to promote and evaluate the commitment of the licensees with safety culture as a whole involves organizational factors and particular attention is directed to the operating organization. This entailed a wide range of activities, including all those related with management of safety performance. Operating Experience Feedback Programme as a tool to enhance safety operation is particularly useful for regulators in the evaluation of the role of S.C. in operating organization. Safety Culture is recognized as a subset of the wider Organizational Culture. Practices that improve organizational effectiveness can also contribute to enhance safety. An effective event investigation methodology is a specific practice, which contributes to a healthy Safety Culture. (author)

  5. Addressing the fundamental issues in reliability evaluation of passive safety of AP1000 for a comparison with active safety of PWR

    International Nuclear Information System (INIS)

    Passive safety systems adopted in advanced Pressurized Water Reactor (PWR), such as AP1000 and EPR, should attain higher reliability than the existing active safety systems of the conventional PWR. The objective of this study is to discuss the fundamental issues relating to the reliability evaluation of AP1000 passive safety systems for a comparison with the active safety systems of conventional PWR, based on several aspects. First, comparisons between conventional PWR and AP1000 are made from the both aspects of safety design and cost reduction. The main differences between these PWR plants exist in the configurations of safety systems: AP1000 employs the passive safety system while reducing the number of active systems. Second, the safety of AP1000 is discussed from the aspect of severe accident prevention in the event of large break loss of coolant accidents (LOCA). Third, detailed fundamental issues on reliability evaluation of AP1000 passive safety systems are discussed qualitatively by using single loop models of safety systems of both PWRs plants. Lastly, methodology to conduct quantitative estimation of dynamic reliability for AP1000 passive safety systems in LOCA condition is discussed, in order to evaluate the reliability of AP1000 in future by a success-path-based reliability analysis method (i.e., GO-FLOW). (author)

  6. Evaluation of agents to detect inflammatory foci using an experimental animal model

    International Nuclear Information System (INIS)

    We have evaluated the propensities of four agents- two metal complexes and two protein species, viz. 67Ga-citrate, 99mTc-citrate, 99mTc-human immunoglobulin (99mTc-HIG); and 99mTc-human serum albumin (99mTc-HSA), for localization of (turpentine- induced) inflammatory lesions in a rat and rabbit animal model systems. All these radiopharmaceuticals showed fairly good uptake in inflammatory lesions. 99mTc-HIG, 99mTc-HSA and 67Ga-citrate showed slower blood clearance and higher liver uptakes. On the other hand 99mTc-citrate demonstrated faster blood clearance and negligible liver and gut accumulation. The respective inflamed/normal muscle (IM/NM) ratios obtained with these agents in this animal model were in the following order: 99mTc-HIG>99mTc-HSA> 67Ga-citrate>99mTc-citrate at 5 h post injection. Although the IM/NM was relatively low in the case of 99mTc-citrate as compared with other radiopharmaceuticals the inflammation could be detected within 1-3 h. post injection because of the higher activities that could be injected with this radiopharmaceutical. Since 99mTc-citrate is predominantly excreted via renal pathway it is rapidly cleared from blood and shows fairly good accumulation in infection/inflammatory lesions at early time periods along with low uptakes in liver and adjacent organs. This agent can therefore be beneficially used to detect the abdominal abscess(es)/inflammation(s) within 1-3 h post injection. Because of its favourable characteristics, physical, biological, clinical, and even cost-effectiveness, it is suggested that 99mTc-citrate could be tried out as an agent for detection of inflammation including abdominal and vertebral abscess(es). (author)

  7. In vitro and ex vivo evaluation of silica-coated super paramagnetic iron oxide nanoparticles (SPION) as biomedical photoacoustic contrast agent

    Science.gov (United States)

    Alwi, Rudolf; Telenkov, Sergey A.; Mandelis, Andreas; Leshuk, Timothy; Gu, Frank; Oladepo, Sulayman; Michaelian, Kirk; Dickie, Kristopher

    2013-03-01

    The employment of contrast agents in photoacoustic imaging has gained significant attention within the past few years for their biomedical applications. In this study, the use of silica-coated superparamagnetic iron oxide (Fe3O4) nanoparticles (SPION) was investigated as a contrast agent in biomedical photoacoustic imaging. SPIONs have been widely used as Food-and-Drug-Administration (FDA)-approved contrast agents for magnetic resonance imaging (MRI) and are known to have an excellent safety profile. Using our frequency-domain photoacoustic correlation technique ("the photoacoustic radar") with modulated laser excitation, we examined the effects of nanoparticle size, concentration and biological medium (e.g. serum, sheep blood) on its photoacoustic response in turbid media (intralipid solution). Maximum detection depth and minimum measurable SPION concentration were determined experimentally. The detection was performed using a single element transducer. The nanoparticle-induced optical contrast ex vivo in dense muscular tissues (avian pectus) was evaluated using a phased array photoacoustic probe and the strong potential of silicacoated SPION as a possible photoacoustic contrast agent was demonstrated. This study opens the way for future clinical applications of nanoparticle-enhanced photoacoustic imaging in cancer therapy.

  8. Evaluation of motorcycle safety strategies using the severity of injuries.

    Science.gov (United States)

    Jung, Soyoung; Xiao, Qin; Yoon, Yoonjin

    2013-10-01

    The growth of motorcycle fatalities in California has been especially prominent, specifically with regard to the 24 and under age group and those aged 45-54. This research quantitatively examined factors associated with motorcyclist fatalities and assessed strategies that could improve motorcyclist safety, specifically focusing on the two age groups mentioned above. Severity of injury was estimated separately for both age groups with multinomial logit models and pseudo-elasticity using motorcycle-related collision data that was collected between 2005 and 2009. The results were compared with motorcyclists aged 35-44, a group that shows a consistent trend of fatalities. This research found that lack or improper use of helmets, victim ejection, alcohol/drug effects, collisions (head-on, broadside, hit-object), and truck involvement were more likely to result in fatal injuries regardless of age group. Weekend and non-peak hour activity was found to have a strong effect in both the younger and older age groups. Two factors, movement of running off the road preceding a collision and multi-vehicle involvement, were found to be statistically significant factors in increasing older motorcyclist fatalities. Use of street lights in the dark was found to decrease the probability of severe injury for older motorcyclists. Driver type of victim, at-fault driver, local road, and speed violation were significant factors in increasing the fatalities of younger motorcyclists. Road conditions and collision location factors were not found to be statistically significant to motorcyclist fatalities. Based on the statistically significant factors identified in this research, the following safety strategies appear to be effective methods of reducing motorcyclist fatalities: public education of alcohol use, promoting helmet use, enforcing heavy vehicle and speed violations, improving roadway facilities, clearer roadway guidance and street lighting systems, and motorcyclist training. PMID

  9. Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

    International Nuclear Information System (INIS)

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

  10. Evaluation of an experimental rat model for comparative studies of bleaching agents

    Directory of Open Access Journals (Sweden)

    Luciano Tavares Angelo Cintra

    2016-02-01

    Full Text Available ABSTRACT Dental materials, in general, are tested in different animal models prior to their clinical use in humans, except for bleaching agents. Objectives To evaluate an experimental rat model for comparative studies of bleaching agents by investigating the influence of different concentrations and application times of H2O2 gel in the pulp tissue during in-office bleaching of rats’ vital teeth. Material and methods The right and left maxillary molars of 50 Wistar rats were bleached with 20% and 35% H2O2 gels, respectively, for 5, 10, 15, 30, or 45 min (n=10 rats/group. Ten animals (control were untreated. The rats were killed after 2 or 30 days, and the maxillae were examined by light microscopy. Inflammation was evaluated by histomorphometric analysis with inflammatory cell counting in the coronal and radicular thirds of the pulp. The counting of fibroblasts was also performed. Scores were attributed to the odontoblastic layer and to vascular changes. The tertiary dentin area and the pulp chamber central area were histomorphometrically measured. Data were compared by the analysis of variance and the Kruskal-Wallis test (p<0.05. Results After 2 days, the amount of inflammatory cells increased in the occlusal third of the coronal pulp until the time of 15 min for both concentrations of bleaching gels. In 30 and 45 min groups of each concentration, the number of inflammatory cells decreased along with the appearance of necrotic areas. After 30 days, a reduction in the pulp chamber central area and an enlargement of tertiary dentin area were observed without the detection of inflammation areas. Conclusion The rat model of extra coronal bleaching showed to be adequate for bleaching protocols studies, as it was possible to observe alterations in the pulp tissues and in the tooth structure caused by different concentrations and periods of application of bleaching agents.

  11. Evaluation of an experimental rat model for comparative studies of bleaching agents

    Science.gov (United States)

    CINTRA, Luciano Tavares Angelo; BENETTI, Francine; FERREIRA, Luciana Louzada; RAHAL, Vanessa; ERVOLINO, Edilson; JACINTO, Rogério de Castilho; GOMES, João Eduardo; BRISO, André Luiz Fraga

    2016-01-01

    ABSTRACT Dental materials in general are tested in different animal models prior to the clinical use in humans, except for bleaching agents. Objectives To evaluate an experimental rat model for comparative studies of bleaching agents, by investigating the influence of different concentrations and application times of H2O2 gel in the pulp tissue during in-office bleaching of rats’ vital teeth. Material and Methods The right and left maxillary molars of 50 Wistar rats were bleached with 20% and 35% H2O2 gels, respectively, for 5, 10, 15, 30, or 45 min (n=10 rats/group). Ten animals were untreated (control). The rats were killed after 2 or 30 days, and the maxillae were examined by light microscopy. Inflammation was evaluated through histomorphometric analysis with inflammatory cell count in the coronal and radicular thirds of the pulp. Fibroblasts were also counted. Scores were attributed to odontoblastic layer and vascular changes. Tertiary dentin area and pulp chamber central area were measured histomorphometrically. Data were compared by analysis of variance and Kruskal-Wallis test (p<0.05). Results After 2 days, the amount of inflammatory cells increased in the coronal pulp occlusal third up to the 15-min application groups of each bleaching gel. In the groups exposed to each concentration for 30 and 45 min, the number of inflammatory cells decreased along with the appearance of necrotic areas. After 30 days, reduction on the pulp chamber central area and enlargement of the tertiary dentin area were observed, without the detection of inflammation areas. Conclusion The rat model of extracoronal bleaching showed to be adequate for studies of bleaching protocols, as it was possible to observe alterations in the pulp tissues and tooth structure caused by different concentrations and application periods of bleaching agents. PMID:27119766

  12. An Evaluation of a Parent Implemented In Situ Pedestrian Safety Skills Intervention for Individuals with Autism.

    Science.gov (United States)

    Harriage, Bethany; Blair, Kwang-Sun Cho; Miltenberger, Raymond

    2016-06-01

    This study evaluated an in situ pedestrian safety skills intervention for three individuals with autism , as implemented by their parents. Specifically, this study examined the utility of behavioral skills training (BST) in helping parents implement most-to-least prompting procedures in training their children to use pedestrian safety skills in community settings. A multiple baseline design across participants was used to assess parent implementation of in situ pedestrian safety skills training as well as the correct use of safety skills independently by the participating individuals with autism. Results indicated that parents implemented in situ, most-to-least prompting procedures with high levels of accuracy across street locations during intervention and fading of BST. All child participants significantly improved their pedestrian safety skills during intervention across all natural street settings. For all three participants, the acquired skills were maintained above baseline levels at 1-month follow-up. PMID:26864158

  13. Preparation and Evaluation of (125I) Daunorubicin as a Potential Agent for Tumor Detection and radiotherapy

    International Nuclear Information System (INIS)

    In this study, the optimization of daunorubicin labeling with iodine-125 and its biological evaluation were described. Daunorubicin was labeled via direct electrophilic substitution using chloramine-T as oxidizing agent. The optimum amounts of reactants were: 40μg daunorubicin, 30μg Chloramine-T and ∼ 19 KBq carrier free Na125I. The labeled daunorubicin was stable for more than 24 hours. Results of the in-vivo evaluation revealed that the tracer, [125I] daunorubicin, tends to localize in tissues with high proliferation rate with preferential accumulation in cancerous tissues. Imaging should be carried at 3 hours post injection. The in-vitro cell growth inhibition assay showed that the effect of [125I] Daunorubicin was stronger than the effect of cold daunorubicin which strongly suggested that its cytotoxicity was mainly due to radiotoxicity rather than chemotherapeutic activity.

  14. Formulation And Evaluation of Topical Aceclofenac Gel Using Different Gelling Agent

    Directory of Open Access Journals (Sweden)

    JAPAN PATEL

    2011-03-01

    Full Text Available Aceclofenac, a non-steroidal anti-inflammatory drug, has been used in the treatment of rheumatoid arthritis and osteoarthritis. In order to decrease the gastric ulcerogenic effects, aceclofenac gels have been developed. This study was conducted to develop a gel formulation of aceclofenac using four types of gelling agents: carbopol, hydroxypropylmethylcellulose(HPMC, carboxymethylcellulose sodium (Na CMC and sodium alginate. Effect of penetration enhancer (propylene glycol on the release has been studied. The gels were evaluated for physical appearance, rheological behavior, drug release and stability. The drug release from all gelling agents through a standard cellophane membrane was evaluated using Keshary-Chien diffusion cell. All gels showed acceptable physical properties concerning color, homogeneity, consistency, spreadability and pH value. Among all the gel formulations, carbopol showed superior drug release than followed by Na CMC, HPMC and sodium alginate. Drug release decreased with increase in polymer concentration. Drug release was not linearly proportional with the concentration of penetration enhancer or co-solvents. Stability studies showed that the physical appearance, rheological properties, and drug release remained unchanged upon storage for two months at ambient conditions.

  15. Safety evaluation of the Greifswald nuclear power plant, unit 1-4

    International Nuclear Information System (INIS)

    The first interim report primarily deals with an evaluation of the pressurized components of the primary loops, especially with the embrittlement of the reactor pressure vessel material. In addition, first estimates concerning the safety design of the plants are made. The second interim report reflects the state of further studies relating to the safety design and the evaluation of operational experiences. The report includes a summarized assessment in which the recommendations cited in the technical chapters are evaluated and subdivided into three categories of backfitting measures. (orig.)

  16. Evaluating the safety of food and color additives with pharmacokinetic data.

    Science.gov (United States)

    Lin, C S

    1992-01-01

    Pharmacokinetic studies are designed to quantify, as a function of time, the processes associated with absorption, distribution, metabolism, and excretion of a chemical in experimental animals or in humans. Such studies have played an important role in drug safety evaluation and could be very useful in the safety evaluation of food and color additives. This presentation provides an overview of the potential use of metabolic and pharmacokinetic data in the design and evaluation of toxicological studies and in the assessment of the potential hazard to humans from exposure to food or color additives. PMID:1515047

  17. Study on safety evaluation of monolithic cement packages of radioactive wastes under deep-sea conditions

    International Nuclear Information System (INIS)

    For sea disposal of the low-level radioactive wastes, the safety of monolithic cement solidified products to be the main solidified waste for dumping was evaluated. Safety evaluation covers the results of integrity test under deep-sea conditions, development of nondestructive inspection and leaching test of nuclides of the above solidified waste. It is concluded that previous evaluation for the sea disposal of radioactive wastes should be more conservative than the real situation, because the cement solidified products have appreciable retardation effect for dispersion of radionuclides and thus the effect of containment is enhanced. (author)

  18. Efficacy and safety of a novel pharmacological stress test agent-higenamine in radionuclide myocardial perfusion imaging: phase Ⅱ clinical trial

    International Nuclear Information System (INIS)

    Objective: To evaluate the effectiveness and safety of higenamine (HG), a pharmaco logical stress agent, for the detection of myocardial ischemia using SPECT. Methods: This study was an open,multi-center, randomized and positively controlled trial with crossover references. It consisted of 120 patients clinically confirmed or suspected of myocardial ischemia. Each patient underwent a resting MPI and two separate stress MPI in a randomized crossover manner with intravenous administration of HG or adenosine (Ad) on different days. The severity and extent of myocardial ischemia were diagnosed on stress MPI. The degree of vascular stenosis in terms of percentage narrowing was measured by CAG (>50% was defined as coronary disease), thus defined as gold standard. The diagnostic efficacy of HG and Ad was compared. Vital signs, routine blood and urine tests,blood biochemical items and side effects were documented for evaluation of procedure safety. Two-sample t test, χ2 or Fisher's exact test, and Kappa test were used. Results: A total of 109 patients completed the trim and CAG. The diagnostic sensitivity, specificity, accuracy, positive predictive value, negative predictive value of HG MPI were 56.1% (32/57), 78.8% (41/52), 67.0%(73/109), 74.4% (32/43) and 62.1% (41/66), respectively, which were not significantly different from those of Ad MPI (52.6% (30/57), 82.7% (43/52), 67.0% (73/109), 76.9% (30/39) and 61.4%(43/70) ; χ2=0-0.2476, all P>0.05). The sensitivity of HG vs Ad MPI in the diagnosis of single-, double-and triple-vessel ischemia was 29.6% (8/27) vs 22.2% (6/27), 64.7% (11/17) vs 64.7% (11/17) and 100% (13/13) vs 100% (13/13), respectively. The concordance between HG and Ad for the detection of LAD, LCX and RCA ischemia was 95.41% (104/109), 97.25% (106/109) and 97.25% (106/109) (Kappa=0.8905, 0.8420 and 0.8874). HG did not induce significant systolic blood pressure change during or after administration. Both HG and Ad could induce temporary decrease of

  19. Development of Basic Key Technologies for Gen IV SFR Safety Evaluation

    International Nuclear Information System (INIS)

    Safety issues and design requirements on control rod worth were identified through the evaluation of safety design characteristics and the preliminary safety evaluation. This results will be taken into account for the conceptual design studies of the demonstration reactor in the next stage. The Level-1 Pasa has been performed and a quantitative Cdf value was produced for the selected design from the several candidates. The inherent safety characteristics of the selected design were evaluated through the DBE and ATWS analyses. A surrogate material for Tru has been selected which is applicable to the study of liquidus/solidus temperature test for the metallic fuel containing Tru. A methodology for the regression analysis with surrogate material has been developed and valuable data on metal fuel liquidus/solidus temperature have been measured. A simple mechanistic model describing a bending of subassemblies has been formulated based on the foreign test data and existing models. Its applicability has been evaluated for the Phenix design. New criteria of the core damage for the SFR PSA were identified. The list of initiating events, system response event tree, and core response event tree, which constitute a PSA methodology for an SFR, have been introduced. By developing the SFR PIRT, phenomenological model features, which have to be satisfied in a safety code, were defined and the PIRT results were applied to the design of the PDRC test facility. Bases for a safety evaluation methodology for the SFR DBEs have been also prepared. A draft version of the topical report on the code for local fault analysis has been completed. Since 2007, the MARS-LMR code has been developed and assessments for model validation with the test data from EBR-II and Phenix reactor have been continued. The code has been applied to the evaluation of passive safety of a conceptual design of Gen IV SFR

  20. Idaho Chemical Processing Plant safety document ICPP hazardous chemical evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Harwood, B.J.

    1993-01-01

    This report presents the results of a hazardous chemical evaluation performed for the Idaho Chemical Processing Plant (ICPP). ICPP tracks chemicals on a computerized database, Haz Track, that contains roughly 2000 individual chemicals. The database contains information about each chemical, such as its form (solid, liquid, or gas); quantity, either in weight or volume; and its location. The Haz Track database was used as the primary starting point for the chemical evaluation presented in this report. The chemical data and results presented here are not intended to provide limits, but to provide a starting point for nonradiological hazards analysis.

  1. Examination of cadmium safety rod thermal test specimens and failure mechanism evaluation

    International Nuclear Information System (INIS)

    The reactor safety rods may be subjected to high temperatures due to gamma heating after the core coolant level has dropped during the ECS phase of a hypothetical LOCA event. Accordingly, an experimental cadmium safety rod testing subtask was established as part of a task to address the response of reactor core components to this accident. Companion reports describe the experiments and a structural evaluation (finite element analysis) of the safety rod. This report deals primarily with the examination of the test specimens, evaluation of possible failure mechanisms, and confirmatory separate effects experiments. It is concluded that the failures observed in the cadmium safety rod thermal tests which occurred at low temperature (T 800 degrees C) with fast thermal ramp rates are concluded to be mechanical in nature without significant environmental degradation. Based on these tests, tasks were initiated to design and manufacture B4C safety rods to replace the cadmium safety rods. The B4C safety rods have been manufactured at this time and it is currently planned to charge them to the reactor in the near future. 60 refs

  2. SRTC criticality safety technical review: Nuclear criticality safety evaluation 94-02, uranium solidification facility pencil tank module spacing

    International Nuclear Information System (INIS)

    Review of NMP-NCS-94-0087, ''Nuclear Criticality Safety Evaluation 94-02: Uranium Solidification Facility Pencil Tank Module Spacing (U), April 18, 1994,'' was requested of the SRTC Applied Physics Group. The NCSE is a criticality assessment to show that the USF process module spacing, as given in Non-Conformance Report SHM-0045, remains safe for operation. The NCSE under review concludes that the module spacing as given in Non-Conformance Report SHM-0045 remains in a critically safe configuration for all normal and single credible abnormal conditions. After a thorough review of the NCSE, this reviewer agrees with that conclusion

  3. Nuclear criticality safety evaluation of large cylinder cleaning operations in X-705, Portsmouth Gaseous diffusion Plant

    International Nuclear Information System (INIS)

    This report evaluates nuclear criticality safety for large cylinder cleaning operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current cleaning procedures and required hardware/equipment is presented, and documentation for large cylinder cleaning operations is identified and described. Control parameters, design features, administrative controls, and safety systems relevant to nuclear criticality are discussed individually, followed by an overall assessment based on the Double Contingency Principle. Recommendations for enhanced safety are suggested, and issues for increased efficiency are presented

  4. Safety evaluation in the development of medical devices and combination products

    CERN Document Server

    Gad, Shayne C

    2008-01-01

    Capturing the growth of the global medical device market in recent years, this practical new guide is essential for all who are responsible for ensuring safety in the use and manufacture of medical devices. It has been extensively updated to reflect significant advances, incorporating combination products and helpful case examples of current real-life problems in the field.The Third Edition explores these key current trends:global device marketscontinually advancing technologythe increasing harmonization of device safety regulation worldwideEach aspect of safety evaluation is considered in ter

  5. Performance Evaluation of a Network the Switch for SMART Safety I and C Systems

    International Nuclear Information System (INIS)

    Process or control signals of safety-grade I and C systems in an NPP(Nuclear Power Plant) are generated periodically. These signals should be delivered to each destination within the predefined response time limit over the safety network. Therefore, communication networks in NPPs should be deterministic. The network switch of a star topology has to be designed to meet the required response time and deterministic characteristics. In this paper, we introduce performance evaluation and design considerations for a safety network switch which is under development

  6. Safety evaluation of saffron stigma (Crocus sativus L.) aqueous extract and crocin in patients with schizophrenia

    OpenAIRE

    Bentolhoda Mousavi; Seyedeh zahra Bathaie; Farbod Fadai; Zabihollah Ashtari; Neda Ali beigi; Sara farhang; Sara Hashempour; Nasim Shahhamzei; Hamid Heidarzadeh

    2015-01-01

    Objectives: Saffron is the stigma of Crocus sativus L., which has the potentials to play a role in the treatment of many diseases. Although many researches are now going on this precious spice, there are few data on saffron safety in human, especially in patients with chronic mental illnesses. This study aimed to evaluate the short-term safety and tolerability of both saffron and crocin (its major constituent) in adult patients with schizophrenia. Materials and Methods: The capsules of saffro...

  7. Evaluation of the EU Mirage project with respect to demands on future safety analyses

    International Nuclear Information System (INIS)

    Potential demands put on future safety assessments of the post-closure stage of nuclear repositories are discussed based on the recent literature. The CEC-coordinated MIRAGE-project (Migration of RAdionuklides in the GEosphere) is part of the Community's ongoing R+D programme for the disposal of nuclear waste. The project was evaluated with respect to demands put on future safety assessments. Recommendations fur future R+D work in the project were given. (orig.)

  8. Safety Evaluation for Packaging 101-SY Hydrogen Mitigation Mixer Pump package

    International Nuclear Information System (INIS)

    This Safety Evaluation for Packaging (SEP) provides analysis and considered necessary to approve a one-time transfer of the 101-SY Hydrogen Mitigation Mixer Pump (HMMP). This SEP will demonstrate that the transfer of the HMMP in a new shipping container will provide an equivalent degree of safety as would be provided by packages meeting US Department of Transportation (DOT)/US Nuclear Regulatory Commission (NRC) requirements. This fulfills onsite, transportation requirements implemented by WHC-CM-2-14

  9. Evaluation of the safety culture in the regulatory activity in Camaguey province

    International Nuclear Information System (INIS)

    Previous studied accomplished in the country have permitted to evaluate the activity of the regulatory body in nuclear safety matter in part of the national territory. These studies did not encompass the Camaguey province. In the work are shown the results of the study in this part of the territory, accomplished as of the survey elaborated by the National Nuclear Safety Center using guides it ASCOT and other documents of the IAEA

  10. Safety Evaluation for Packaging 101-SY Hydrogen Mitigation Mixer Pump package

    Energy Technology Data Exchange (ETDEWEB)

    Carlstrom, R.F.

    1994-10-05

    This Safety Evaluation for Packaging (SEP) provides analysis and considered necessary to approve a one-time transfer of the 101-SY Hydrogen Mitigation Mixer Pump (HMMP). This SEP will demonstrate that the transfer of the HMMP in a new shipping container will provide an equivalent degree of safety as would be provided by packages meeting US Department of Transportation (DOT)/US Nuclear Regulatory Commission (NRC) requirements. This fulfills onsite, transportation requirements implemented by WHC-CM-2-14.

  11. Multi-criteria analysis for evaluating the radiological and ecological safety measures in radioactive waste management

    International Nuclear Information System (INIS)

    A methodological approach is presented for multicriterial evaluating the effectiveness of radiation ecological safety measures during radioactive waste management. The approach is based on multicriterial analysis with consideration of radiological, ecological, social, economical consequences of various safety measures. The application of the multicriterial approach is demonstrated taking as an example of decision-making on the most effective actions for rehabilitation of a water subject, contaminated with radionuclides

  12. Non-Clinical Safety Evaluation of Intranasal Iota-Carrageenan

    Science.gov (United States)

    Hebar, Alexandra; Koller, Christiane; Seifert, Jan-Marcus; Chabicovsky, Monika; Bodenteich, Angelika; Bernkop-Schnürch, Andreas; Grassauer, Andreas; Prieschl-Grassauer, Eva

    2015-01-01

    Carrageenan has been widely used as food additive for decades and therefore, an extended oral data set is available in the public domain. Less data are available for other routes of administration, especially intranasal administration. The current publication describes the non-clinical safety and toxicity of native (non-degraded) iota-carrageenan when applied intranasally or via inhalation. Intranasally applied iota-carrageenan is a topically applied, locally acting compound with no need of systemic bioavailability for the drug’s action. Animal experiments included repeated dose local tolerance and toxicity studies with intranasally applied 0.12% iota-carrageenan for 7 or 28 days in New Zealand White rabbits and nebulized 0.12% iota-carrageenan administered to F344 rats for 7 days. Permeation studies revealed no penetration of iota-carrageenan across nasal mucosa, demonstrating that iota-carrageenan does not reach the blood stream. Consistent with this, no relevant toxic or secondary pharmacological effects due to systemic exposure were observed in the rabbit or rat repeated dose toxicity studies. Data do not provide any evidence for local intolerance or toxicity, when carrageenan is applied intranasally or by inhalation. No signs for immunogenicity or immunotoxicity have been observed in the in vivo studies. This is substantiated by in vitro assays showing no stimulation of a panel of pro-inflammatory cytokines by iota-carrageenan. In conclusion, 0.12% iota-carrageenan is safe for clinical use via intranasal application. PMID:25875737

  13. Safety evaluation of neem (Azadirachta indica) derived pesticides.

    Science.gov (United States)

    Boeke, Sara J; Boersma, Marelle G; Alink, Gerrit M; van Loon, Joop J A; van Huis, Arnold; Dicke, Marcel; Rietjens, Ivonne M C M

    2004-09-01

    The neem tree, Azadirachta indica, provides many useful compounds that are used as pesticides and could be applied to protect stored seeds against insects. However in addition to possible beneficial health effects, such as blood sugar lowering properties, anti-parasitic, anti-inflammatory, anti-ulcer and hepatoprotective effects, also toxic effects are described. In this study we present a review of the toxicological data from human and animal studies with oral administration of different neem-based preparations. The non-aqueous extracts appear to be the most toxic neem-based products, with an estimated safe dose (ESD) of 0.002 and 12.5 microg/kg bw/day. Less toxic are the unprocessed materials seed oil and the aqueous extracts (ESD 0.26 and 0.3 mg/kg bw/day, 2 microl/kg bw/day respectively). Most of the pure compounds show a relatively low toxicity (ESD azadirachtin 15 mg/kg bw/day). For all preparations, reversible effect on reproduction of both male and female mammals seem to be the most important toxic effects upon sub-acute or chronic exposure. From the available data, safety assessments for the various neem-derived preparations were made and the outcomes are compared to the ingestion of residues on food treated with neem preparations as insecticides. This leads to the conclusion that, if applied with care, use of neem derived pesticides as an insecticide should not be discouraged. PMID:15261960

  14. Evaluation of unnatural cyclic amino acids as boron delivery agents for treatment of melanomas and gliomas

    International Nuclear Information System (INIS)

    Unnatural cyclic amino acids (UNAAs) are a new class of boron delivery agents that are in a pre-clinical stage of evaluation. In the present study, the biodistribution of racemic forms of the cis- and trans-isomers of the boronated UNAA 1-amino-3-boronocyclopentanecarboxylic acid (ABCPC) and 1-amino-3-boronocycloheptanecarboxylic acid (ABCHC) were evaluted in B16 melanoma bearing mice and this was compared to L-p-boronophenylalanine (BPA). Boron concentrations were determined by inductively coupled plasma-optical emission spectroscopy (ICP-OES) at 2.5 h following intraperitoneal (i.p.) injection of the test agents at a concentration equivalent to 24 mg/B/kg. While all compounds attained comparable tumor boron concentrations, the tumor/blood (T/Bl) boron concentration ratios were far superior for both cis-ABCPC and cis-ABCHC compared to BPA (T/Bl=16.4, and 15.1 vs. 5.4). Secondary ion mass spectrometry (SIMS) imaging revealed that the cis-ABCPC delivered boron to the nuclei, as well as the cytoplasm of B16 cells. Next, a biodistribution study of cis-ABCPC and BPA was carried out in F98 glioma bearing rats following i.p. administration. Both compounds attained comparable tumor boron concentrations but the tumor/brain (T/Br) boron ratio was superior for cis-ABCPC compared to BPA (6 vs. 3.3). Since UNAAs are water soluble and cannot be metabolized by tumor cells, they could be potentially more effective boron delivery agents than BPA. Our data suggest that further studies are warranted to evaluate these compounds prior to the initiation of clinical studies. - Highlights: • Unnatural cyclic amino acids (UNAAs) are a new class of boron delivery agents for neutron capture therapy. • ABCPC and ABCHC attained higher tumor/blood ratios vs. BPA in B16 melanoma bearing mice. • The tumor/brain ratio of cis-ABCPC was superior to BPA (6 vs. 3.3) suggesting that further studies are warranted

  15. Safety evaluation of cosmetics in the EU. Reality and challenges for the toxicologist.

    Science.gov (United States)

    Pauwels, Marleen; Rogiers, Vera

    2004-06-15

    Council Directive 76/768/EEC, its seven amendments and 30 adaptations to technical progress form the basis of the cosmetic EU legislation today. There are actually four key principles for safety in the cosmetic legislation. (i) The full responsibility for the safety of cosmetics for human health is placed on the manufacturer, first importer in the EU or marketer. (ii) The safety evaluation of finished products is based on safety of individual ingredients, more specifically on their chemical structure, toxicological profile and their level of exposure. (iii) A compilation of information on each cosmetic product (dossier) must be kept readily available for inspection by the competent authorities of the Member State concerned. This information source, usually called a technical information file (TIF) or product information file/requirements (PIF(R)), contains, as the most important part, the safety assessment of the product undersigned by a competent safety assessor. (iv) The use of validated replacement alternative methods instead of animal testing forms the 4th key principle for safety of cosmetic products on the EU market. The 7th amendment imposes strict deadlines for the abolition of animal in vivo studies on cosmetic ingredients. These legal requirements induce a number of important challenges for the cosmetic industry and more specifically for the toxicologist involved as safety assessor. PMID:15177635

  16. An evaluation of an airline cabin safety education program for elementary school children.

    Science.gov (United States)

    Liao, Meng-Yuan

    2014-04-01

    The knowledge, attitude, and behavior intentions of elementary school students about airline cabin safety before and after they took a specially designed safety education course were examined. A safety education program was designed for school-age children based on the cabin safety briefings airlines given to their passengers, as well as on lessons learned from emergency evacuations. The course is presented in three modes: a lecture, a demonstration, and then a film. A two-step survey was used for this empirical study: an illustrated multiple-choice questionnaire before the program, and, upon completion, the same questionnaire to assess its effectiveness. Before the program, there were significant differences in knowledge and attitude based on school locations and the frequency that students had traveled by air. After the course, students showed significant improvement in safety knowledge, attitude, and their behavior intention toward safety. Demographic factors, such as gender and grade, also affected the effectiveness of safety education. The study also showed that having the instructor directly interact with students by lecturing is far more effective than presenting the information using only video media. A long-term evaluation, the effectiveness of the program, using TV or video accessible on the Internet to deliver a cabin safety program, and a control group to eliminate potential extraneous factors are suggested for future studies. PMID:24286820

  17. The 'PROCESO' index: a new methodology for the evaluation of operational safety in the chemical industry

    International Nuclear Information System (INIS)

    The acknowledgement of industrial installations as complex systems in the early 1980s outstands as a milestone in the path to operational safety. Process plants are social-technical complex systems of a dynamic nature, whose properties depend not only on their components, but also on the inter-relations among them. A comprehensive assessment of operational safety requires a systemic approach, i.e. an integrated framework that includes all the relevant factors influencing safety. Risk analysis methodologies and safety management systems head the list of methods that point in this direction, but they normally require important plant resources. As a consequence, their use is frequently restricted to especially dangerous processes often driven by compliance with legal requirements. In this work a new safety index for the chemical industry, termed the 'Proceso' Index (standing for the Spanish terms for PROCedure for the Evaluation of Operational Safety), has been developed. PROCESO is based on the principles of systems theory, has a tree-like structure and considers 25 areas to guide the review of plant safety. The method uses indicators whose respective weight values have been obtained via an expert judgement technique. This paper describes the steps followed to develop this new Operational Safety Index, explains its structure and illustrates its application to process plants

  18. Key techniques for evaluation of safety monitoring sensors in water conservancy and hydropower engineering

    Directory of Open Access Journals (Sweden)

    Yan XIANG

    2012-12-01

    Full Text Available For the evaluation of construction quality and the verification of the design of water conservancy and hydropower engineering projects, and especially for the control of dam safety operation behavior, safety monitoring sensors are employed in a majority of engineering projects. These sensors are used to monitor the project during the dam construction and operation periods, and play an important role in reservoir safety operation and producing benefits. With the changing of operating environments and run-time of projects, there are some factors affecting the operation and management of projects, such as a certain amount of damaged sensors and instability of the measured data. Therefore, it is urgent to evaluate existing safety monitoring sensors in water conservancy and hydropower engineering projects. However, there are neither standards nor evaluation guidelines at present. Based on engineering practice, this study examined some key techniques for the evaluation of safety monitoring sensors, including the evaluation process of the safety monitoring system, on-site detection methods of two typical pieces of equipment, the differential resistor sensor and vibrating wire sensor, the on-site detection methods of communication cable faults, and a validity test of the sensor measured data. These key techniques were applied in the Xiaolangdi Water Control Project and Xiaoxi Hydropower Project. The results show that the measured data of a majority of sensors are reliable and reasonable, and can reasonably reflect the structural change behavior in the project operating process, indicating that the availabilities of the safety monitoring sensors of the two projects are high.

  19. SAFETY

    CERN Multimedia

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  20. SAFETY

    CERN Multimedia

    C. Schaefer and N. Dupont

    2013-01-01

      “Safety is the highest priority”: this statement from CERN is endorsed by the CMS management. An interpretation of this statement may bring you to the conclusion that you should stop working in order to avoid risks. If the safety is the priority, work is not! This would be a misunderstanding and misinterpretation. One should understand that “working safely” or “operating safely” is the priority at CERN. CERN personnel are exposed to different hazards on many levels on a daily basis. However, risk analyses and assessments are done in order to limit the number and the gravity of accidents. For example, this process takes place each time you cross the road. The hazard is the moving vehicle, the stake is you and the risk might be the risk of collision between both. The same principle has to be applied during our daily work. In particular, keeping in mind the general principles of prevention defined in the late 1980s. These principles wer...

  1. Structural safety evaluation based on system identification approaches

    International Nuclear Information System (INIS)

    The papers are classified in an arbitrary manner. Several papers cover more than one item. In Item No. 1 the tools for the detection and localization of structure modifications by identification methods are discussed in general. The discussion of system identification approaches is included in Item No. 2. Instrumentation and data processing are important parts of identification, since the quality of the results depends on them. The interaction between the results of system identification and damage evaluation is discussed in Item No. 3. Here probabilistic methods and related mathematics such as fuzzy sets are presented. Under Item No. 4 concepts of damage evaluation are discussed. Ideally both linear and nonlinear models should be considered. (DG)

  2. DNA vaccination for rabies: Evaluation of preclinical safety and toxicology

    OpenAIRE

    Rajni Garg; Manpreet Kaur; Ankur Saxena; Rakesh Bhatnagar

    2014-01-01

    The worldwide incidence of rabies and high rates of therapy failure, despite availability of effective vaccines indicate the need for timely and improved prophylactic approaches. DNA vaccination based on optimized formulation of lysosome-targeted glycoprotein of the rabies virus provides potential platform for preventing and controlling rabies. As per the pre-clinical requirements, listed in guidelines of Schedule Y, FDA and that of The European Agency for evaluation of Medicinal Products; we...

  3. OPTIMIZATION AND EVALUATION OF MICROBE FORTIFIED COMPOSTS AS BIOCONTROL AGENTS AGAINST PHYTOPATHOGENIC FUNGI

    Directory of Open Access Journals (Sweden)

    Ajinath S. Dukare

    2013-04-01

    Full Text Available A set of bacterial (B1-10 and cyanobacterial strains (C1-C14 were evaluated for their fungicidal activity against selected phytopathogenic fungi - Fusarium solani, Fusarium oxysporum, Fusarium oxysporum lycopersici, Fusarium moniliforme, Pythium debaryanum and Rhizoctonia solani. Further, they were used to amend rice straw compost and the filtrates were evaluated against the selected fungi after 10 and 20 days of incubation. Six promising strains, including three bacterial and three cyanobacterial strains were selected and characterised in terms of activity of hydrolytic enzymes. Interestingly, C12 strain (Anabaena spp. showed highest activity of cellulase, chitosanase and β 1, 3 glucanase. These strains were then evaluated by optimization of inoculum levels (1-5% in the rice straw compost. The strains B3, B5, C8 and C12 were observed to be most promising as they exhibited inhibition and significantly higher activity of microbiological parameters and hydrolytic enzymes at 1-2% level of inoculum in the compost. Further investigations are being undertaken to scale up the development of compost based biocontrol agents using these strains for evaluation at field level.

  4. Evaluation of the safety margins during shutdown for NPP Krsko

    International Nuclear Information System (INIS)

    In the paper the results of RELAP5/mod3.3 calculations of critical parameters during shutdown for NPP Krsko are presented. Conservative evaluations have been performed at NPP Krsko to determine the minimum configuration of systems required for the safe shutdown operation. Critical parameters in these evaluations are defined as the time to start of the boiling and the time of the core dry-out. In order to have better insight into the available margins, the best estimate code RELAP5/mod3.3 has been used to calculate the same parameters. The analyzed transient is the loss of the Residual Heat Removal (RHR) system, which is used to remove decay heat during shutdown conditions. Several configurations that include open and closed Reactor Coolant System (RCS) were considered in the evaluation. The RELAP5/mod3.3 analysis of the loss of the RHR system has been performed for the following cases: 1) RCS closed and water solid, 2) RCS closed and partially drained, 3) Pressurizer manway open, Steam Generator (SG) U tubes partially drained, 4) Pressurizer and SG manways open, SG U tubes completely drained, 5) Pressurizer manway open, SGs drained, SG nozzle dams installed and 6) SG nozzle dams installed, pressurizer manway open, 1 inch break at RHR pump discharge in the loop with pressurizer. Both RHR trains were assumed in operation prior to start of the transient. The maximum average steady state temperature for all analyzed cases was limited to 333 K. (author)

  5. Comparative assessment of nanomaterial definitions and safety evaluation considerations.

    Science.gov (United States)

    Boverhof, Darrell R; Bramante, Christina M; Butala, John H; Clancy, Shaun F; Lafranconi, Mark; West, Jay; Gordon, Steve C

    2015-10-01

    Nanomaterials continue to bring promising advances to science and technology. In concert have come calls for increased regulatory oversight to ensure their appropriate identification and evaluation, which has led to extensive discussions about nanomaterial definitions. Numerous nanomaterial definitions have been proposed by government, industry, and standards organizations. We conducted a comprehensive comparative assessment of existing nanomaterial definitions put forward by governments to highlight their similarities and differences. We found that the size limits used in different definitions were inconsistent, as were considerations of other elements, including agglomerates and aggregates, distributional thresholds, novel properties, and solubility. Other important differences included consideration of number size distributions versus weight distributions and natural versus intentionally-manufactured materials. Overall, the definitions we compared were not in alignment, which may lead to inconsistent identification and evaluation of nanomaterials and could have adverse impacts on commerce and public perceptions of nanotechnology. We recommend a set of considerations that future discussions of nanomaterial definitions should consider for describing materials and assessing their potential for health and environmental impacts using risk-based approaches within existing assessment frameworks. Our intent is to initiate a dialogue aimed at achieving greater clarity in identifying those nanomaterials that may require additional evaluation, not to propose a formal definition. PMID:26111608

  6. Evaluation of a liquid embolization agent (Onyx) for transcatheter embolization for renal vascular lesions

    Energy Technology Data Exchange (ETDEWEB)

    Rennert, Janine; Herold, T.; Schreyer, A.G.; Jung, E.M.; Mueller-Wille, R.; Zorger, N. [Inst. fuer Roentgendiagnostik, Klinikum der Univ. Regensburg (Germany); Banas, B.; Feuerbach, S. [Medizinische Klinik, Nephrologie, Univ. Regensburg (Germany); Lenhart, M. [Klinik fuer Diagnostische und Interventionelle Radiologie, Sozialstiftung Bamberg (Germany)

    2009-10-15

    Purpose: to evaluate the therapeutic outcome after endovascular treatment of renal vascular lesions using the liquid embolization agent, Onyx. Materials and methods: between 2004 and 2008 nine patients with renal vascular lesions were treated with transcatheter arterial embolization using Onyx. The renal vascular lesions consisted of 4 AV-fistulas, a pseudoaneurysm, bleeding from a single subsegmental artery, diffuse parenchymal bleeding after trauma, septic embolizations and multiple aneurysms in endocarditis. All patients underwent selective angiography of the renal artery. A dimethyl sulfoxide (DMSO)-compatible microcatheter was used and Onyx was injected. The technical and clinical success rate, examination time and procedure-related complications were documented. Results: the overall technical and clinical success rate was 100%. One patient had to be treated twice due to recurrent bleeding after an accidental puncture with a drainage catheter. No loss of viable renal tissue occurred in 4 cases. In 4 patients mild to moderate parenchyma loss was noted. In one patient having diffuse renal bleeding, occlusion of the main renal artery was performed. No procedure-related complications were noted. The mean examination time was 16.17 min when treating with Onyx alone and 60 min when using a combination of Onyx and coils. Within an average follow-up period of 21 months, no recurrent renal bleeding or recurrent AV-fistulas occurred. Conclusion: Onyx is an effective embolization agent for the treatment of renal vascular lesions. It allows controlled and quick application with low complication rates and a short examination time as a standalone agent or in combination with coils. (orig.)

  7. Evaluation of a liquid embolization agent (Onyx) for transcatheter embolization for renal vascular lesions

    International Nuclear Information System (INIS)

    Purpose: to evaluate the therapeutic outcome after endovascular treatment of renal vascular lesions using the liquid embolization agent, Onyx. Materials and methods: between 2004 and 2008 nine patients with renal vascular lesions were treated with transcatheter arterial embolization using Onyx. The renal vascular lesions consisted of 4 AV-fistulas, a pseudoaneurysm, bleeding from a single subsegmental artery, diffuse parenchymal bleeding after trauma, septic embolizations and multiple aneurysms in endocarditis. All patients underwent selective angiography of the renal artery. A dimethyl sulfoxide (DMSO)-compatible microcatheter was used and Onyx was injected. The technical and clinical success rate, examination time and procedure-related complications were documented. Results: the overall technical and clinical success rate was 100%. One patient had to be treated twice due to recurrent bleeding after an accidental puncture with a drainage catheter. No loss of viable renal tissue occurred in 4 cases. In 4 patients mild to moderate parenchyma loss was noted. In one patient having diffuse renal bleeding, occlusion of the main renal artery was performed. No procedure-related complications were noted. The mean examination time was 16.17 min when treating with Onyx alone and 60 min when using a combination of Onyx and coils. Within an average follow-up period of 21 months, no recurrent renal bleeding or recurrent AV-fistulas occurred. Conclusion: Onyx is an effective embolization agent for the treatment of renal vascular lesions. It allows controlled and quick application with low complication rates and a short examination time as a standalone agent or in combination with coils. (orig.)

  8. Use of Yeast Chemigenomics and COXEN Informatics in Preclinical Evaluation of Anticancer Agents

    Directory of Open Access Journals (Sweden)

    Steven C. Smith

    2011-01-01

    Full Text Available Bladder cancer metastasis is virtually incurable with current platinum-based chemotherapy. We used the novel COXEN informatic approach for in silico drug discovery and identified NSC-637993 and NSC-645809 (C1311, both imidazoacridinones, as agents with high-predicted activity in human bladder cancer. Because even highly effective monotherapy is unlikely to cure most patients with metastasis and NSC-645809 is undergoing clinical trials in other tumor types, we sought to develop the basis for use of C1311 in rational combination with other agents in bladder cancer. Here, we demonstrate in 40 human bladder cancer cells that the in vitro cytotoxicity profile for C1311 correlates with that of NSC-637993 and compares favorably to that of standard of care chemotherapeutics. Using genomewide patterns of synthetic lethality of C1311 with open reading frame knockouts in budding yeast, we determined that combining C1311 with a taxane could provide mechanistically rational combinations. To determine the preclinical relevance of these yeast findings, we evaluated C1311 singly and in doublet combination with paclitaxel in human bladder cancer in the in vivo hollow fiber assay and observed efficacy. By applying COXEN to gene expression data from 40 bladder cancer cell lines and 30 human tumors with associated clinical response data to platinum-based chemotherapy, we provide evidence that signatures of C1311 sensitivity exist within nonresponders to this regimen. Coupling COXEN and yeast chemigenomics provides rational combinations with C1311 and tumor genomic signatures that can be used to select bladder cancer patients for clinical trials with this agent.

  9. The Activities of the International Criticality Safety Benchmark Evaluation Project (ICSBEP)

    Energy Technology Data Exchange (ETDEWEB)

    Briggs, Joseph Blair

    2001-10-01

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organization for Economic Cooperation and Development (OECD) – Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Spain, and Israel are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled “International Handbook of Evaluated Criticality Safety Benchmark Experiments”. The 2001 Edition of the Handbook contains benchmark specifications for 2642 critical or subcritical configurations that are intended for use in validation efforts and for testing basic nuclear data.

  10. Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    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 2010, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes such as core seismic analysis code, core safety analysis code and core damage analysis code were carried out according to the plan. 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, and the seismic PSA to evaluate residual risk was studied. (author)

  11. Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor (Annual safety research report, JFY 2011)

    International Nuclear Information System (INIS)

    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 2011, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes such as core seismic analysis code, core safety analysis code and core damage analysis code were earned out according to the plan. 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, and the seismic PSA to evaluate residual risk was studied. (author)

  12. [Establish research model of post-marketing clinical safety evaluation for Chinese patent medicine].

    Science.gov (United States)

    Zheng, Wen-ke; Liu, Zhi; Lei, Xiang; Tian, Ran; Zheng, Rui; Li, Nan; Ren, Jing-tian; Du, Xiao-xi; Shang, Hong-cai

    2015-09-01

    The safety of Chinese patent medicine has become a focus of social. It is necessary to carry out work on post-marketing clinical safety evaluation for Chinese patent medicine. However, there have no criterions to guide the related research, it is urgent to set up a model and method to guide the practice for related research. According to a series of clinical research, we put forward some views, which contained clear and definite the objective and content of clinical safety evaluation, the work flow should be determined, make a list of items for safety evaluation project, and put forward the three level classification of risk control. We set up a model of post-marketing clinical safety evaluation for Chinese patent medicine. Based this model, the list of items can be used for ranking medicine risks, and then take steps for different risks, aims to lower the app:ds:risksrisk level. At last, the medicine can be managed by five steps in sequence. The five steps are, collect risk signal, risk recognition, risk assessment, risk management, and aftereffect assessment. We hope to provide new ideas for the future research. PMID:26983223

  13. Reasoning about Risk in Agent's Deliberation Process: a Jadex Implementation

    OpenAIRE

    Asnar, Yudistira; Giorgini, Paolo; Zannone, Nicola

    2006-01-01

    Autonomous agents and multi-agent systems have been proved to be useful in several safety-critical applications. However, in current agent architectures (particularly BDI architectures) the deliberation process does not include any form of risk analysis. In this paper, we propose guidelines to implement Tropos Goal-Risk reasoning. Our proposal aims at introducing risk reasoning in the deliberation process of a BDI agent so that the overall set of possible plans is evaluated with respect to ri...

  14. Development of the safety evaluation system in the respects of organizational factors and workers' consciousness. Pt. 1. Study of validities of functions for necessary evaluation and results obtained

    International Nuclear Information System (INIS)

    CRIEPI decided to develop the safety evaluation system to investigate the safety level of the industrial sites due to questionnaires of organizational climate, safety managements, and workers' safety consciousness to workers. This report describes the questionnaire survey to apply to the domestic nuclear power plant for using obtained results as a fundamental data in order to construct the safety evaluation system. This system will be used for promoting safety culture in organizations of nuclear power plants. The questionnaire survey was conducted to 14 nuclear power stations for understanding the present status relating to safety issues. This questionnaire involves 122 items classified into following three categories: (1) safety awareness and behavior of plant personnel; (2) safety management; (3) organizational climate, based on the model considering contributing factor groups to safety culture. Obtained results were analyzed by statistical method to prepare functions of evaluation. Additionally, by applying a multivariate analysis, it was possible to extract several crucial factors influencing safety performance and to find a comprehensive safety indicator representing total organizational safety level. Significant relations were identified between accident rates (both labor accidents and facility failures) and above comprehensive safety indicator. Next, 122 questionnaire items were classified into 20 major safety factors to grasp the safety profiles of each site. This profile is considered as indicating the features of each site and also indicating the direction of progress for improvement of safety situation in the site. These findings can be reflected in developing the safety evaluation system, by confirming the validity of the evaluation method and giving specific functions. (author)

  15. Insights into safety attitudes at U.S. nuclear plants from onsite evaluations of operating events

    International Nuclear Information System (INIS)

    In 1990, the United States Nuclear Regulatory Commission's (U.S. NRC) Office for Analysis and Evaluation of Operational Data (AEOD) established a program to conduct onsite evaluations of human performance in operating events. About 20 such evaluations have been conducted. In addition, AEOD staff have participated in event reviews conducted by U.S. NRC augmented inspection teams. By interviewing key operations personnel and understanding their actions and related decisions during an operating event, insight can be gained into the site's safety culture. Further investigation, evaluation, and understanding of the root causes of the factors that influenced operator performance can yield insight into the licensee's priorities, decision-making processes, communications, and effectiveness of problem identification and corrective action processes, including management effectiveness. This paper provides an overview of AEOD's onsite human performance evaluation program and results from these evaluations. While the results from an individual site visit do not provide a detailed safety culture assessment, such visits do yield insight into a site's safety culture. By incorporating these techniques into routine event investigations, it is possible to identify emerging safety culture issues. (author)

  16. Synthesis and evaluation of 99mTc-moxifloxacin, a potential infection specific imaging agent

    International Nuclear Information System (INIS)

    To synthesize and evaluate a 99mTc labeled fluroquinolone, moxifloxacin as a potential bacteria specific infection imaging agent. A radiolabeling formulation including moxifloxacin, [MoxicipTM injection, Cipla] (4 mg), sodium pertechnetate and stannous chloride (5 μg) gave the best radiolabeling efficiency and moderately stable labeled 99mTc moxifloxacin. Quality control analysis was performed by ITLC. Rats and rabbit with infectious intramuscular lesions induced in either thigh with E. Colli were used for studying biodistribution and scintigraphic imaging of the labeled product. Imaging of an infected thigh of a rabbit was performed with a γ-camera at various intervals. A good radiolabeling efficiency (90-95%) was obtained within 5 min. No purification of the labeled product was done. Labeled product retained its radiochemical purity upto 85% even at 3 h. Scintigraphy showed uptake in infectious lesions at 30 min after injection, which remains constant upto 3 h study. Abscess-to-muscle ratios were 1.60, 1.62, 1.74 and 1.75 at 30 min, 1, 2 and 3 h, respectively. Thus, 99mTc moxifloxacin, a new potential radiopharmaceutical has been developed for infection imaging agent.

  17. Design, Synthesis, and Biological Evaluation of Novel Selenium (Se-NSAID) Molecules as Anticancer Agents.

    Science.gov (United States)

    Plano, Daniel; Karelia, Deepkamal N; Pandey, Manoj K; Spallholz, Julian E; Amin, Shantu; Sharma, Arun K

    2016-03-10

    The synthesis and anticancer evaluation of novel selenium-nonsteroidal anti-inflammatory drug (Se-NSAID) hybrid molecules are reported. The Se-aspirin analogue 8 was identified as the most effective agent in reducing the viability of different cancer cell lines, particularly colorectal cancer (CRC) cells, was more selective toward cancer cells than normal cells, and was >10 times more potent than 5-FU, the current therapy for CRC. Compound 8 inhibits CRC growth via the inhibition of the cell cycle in G1 and G2/M phases and reduces the cell cycle markers like cyclin E1 and B1 in a dose dependent manner; the inhibition of the cell cycle may be dependent on the ability of 8 to induce p21 expression. Furthermore, 8 induces apoptosis by activating caspase 3/7 and PARP cleavage, and its longer exposure causes increase in intracellular ROS levels in CRC cells. Taken together, 8 has the potential to be developed further as a chemotherapeutic agent for CRC. PMID:26750401

  18. Synthesis and evaluation of {sup 99m}Tc-moxifloxacin, a potential infection specific imaging agent

    Energy Technology Data Exchange (ETDEWEB)

    Chattopadhyay, Sankha [Radiopharmaceuticals Laboratory, Board of Radiation and Isotope Technology, Variable Energy Cyclotron Centre, 1/AF, Bidhan Nagar, Kolkata 700 064 (India)], E-mail: sankha@veccal.ernet.in; Saha Das, Sujata [Radiopharmaceuticals Laboratory, Board of Radiation and Isotope Technology, Variable Energy Cyclotron Centre, 1/AF, Bidhan Nagar, Kolkata 700 064 (India); Chandra, Susmita; De, Kakali; Mishra, Mridula [Nuclear Medicine Department, Indian Institute of Chemical Biology, Kolkata (India); Ranjan Sarkar, Bharat; Sinha, Samarendu; Ganguly, Shantanu [Regional Radiation Medicine Centre, Variable Energy Cyclotron Centre, Kolkata (India)

    2010-02-15

    To synthesize and evaluate a {sup 99m}Tc labeled fluroquinolone, moxifloxacin as a potential bacteria specific infection imaging agent. A radiolabeling formulation including moxifloxacin, [Moxicip{sup TM} injection, Cipla] (4 mg), sodium pertechnetate and stannous chloride (5 {mu}g) gave the best radiolabeling efficiency and moderately stable labeled {sup 99m}Tc moxifloxacin. Quality control analysis was performed by ITLC. Rats and rabbit with infectious intramuscular lesions induced in either thigh with E. Colli were used for studying biodistribution and scintigraphic imaging of the labeled product. Imaging of an infected thigh of a rabbit was performed with a {gamma}-camera at various intervals. A good radiolabeling efficiency (90-95%) was obtained within 5 min. No purification of the labeled product was done. Labeled product retained its radiochemical purity upto 85% even at 3 h. Scintigraphy showed uptake in infectious lesions at 30 min after injection, which remains constant upto 3 h study. Abscess-to-muscle ratios were 1.60, 1.62, 1.74 and 1.75 at 30 min, 1, 2 and 3 h, respectively. Thus, {sup 99m}Tc moxifloxacin, a new potential radiopharmaceutical has been developed for infection imaging agent.

  19. Synthesis and Evaluation of Ester Derivatives of 10-Hydroxycanthin-6-one as Potential Antimicrobial Agents.

    Science.gov (United States)

    Zhao, Fei; Dai, Jiang-Kun; Liu, Dan; Wang, Shi-Jun; Wang, Jun-Ru

    2016-01-01

    As part of our continuing research on canthin-6-one antimicrobial agents, a new series of ester derivatives of 10-hydroxycanthin-6-one were synthesized using a simple and effective synthetic route. The structure of each compound was characterized by NMR, ESI-MS, FT-IR, UV, and elemental analysis. The antimicrobial activity of these compounds against three phytopathogenic fungi (Alternaria solani, Fusarium graminearum, and Fusarium solani) and four bacteria (Bacillus cereus, Bacillus subtilis, Ralstonia solanacearum, and Pseudomonas syringae) were evaluated using the mycelium linear growth rate method and micro-broth dilution method, respectively. The structure-activity relationship is discussed. Of the tested compounds, 4 and 7s displayed significant antifungal activity against F. graminearum, with inhibition rates of 100% at a concentration of 50 μg/mL. Compounds 5, 7s, and 7t showed the best inhibitory activity against all the tested bacteria, with minimum inhibitory concentrations (MICs) between 3.91 and 31.25 μg/mL. Thus, 7s emerged as a promising lead compound for the development of novel canthine-6-one antimicrobial agents. PMID:27007362

  20. An overview of the current methodologies used for evaluation of aphrodisiac agents

    Institute of Scientific and Technical Information of China (English)

    Ramandeep Singh; Ashraf Ali; G Jeyabalan; Alok Semwal; Jaikishan

    2013-01-01

    Discoveries in the past two decades have continued to improve our understanding of the pathophysiology of erectile dysfunction disease and animal models have played a significant role to define the basic mechanisms of erectile dysfunction treatment.Bothin vitroandin vivomodels have been developed in the past years to study the aphrodisiac agents.Methods that are used in aphrodisiac study can be categorized into physical methods including male sexual behavior (mount frequency, mount latency, intromission frequency, intromission latency, ejaculation frequency, post-ejaculatory interval, couplatory rate, index of libido, computed male sexual behavior parameter), pendiculation study, orientation behavior, determination of hesitation time & attraction towards female, test of potency, test for libido, penile microcirculation study, Intracavernous pressure study and biochemical methods, histopathology, sperm count,Fructose content in seminal vesicles, sperm preservation, organ weight, hormonal determination, assay of nitric oxide synthase, In vitro nitric oxide release & androgen receptor protein.This review aims to highlight some of the new and currently used experimental models that are used for the evaluation of aphrodisiac agents.