Implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Stewart, L.; Tonkay, D.

2004-01-01

This paper discusses the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention: establishes a commitment with respect to safe management of spent nuclear fuel and radioactive waste; requires the Parties to ''take appropriate steps'' to ensure the safety of their spent fuel and waste management activities, but does not delineate standards the Parties must meet; and seeks to attain, through its Contracting Parties, a higher level of safety with respect to management of their spent nuclear fuel, disused sealed sources, and radioactive waste

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report from Norway

International Nuclear Information System (INIS)

2006-05-01

This report is the Norwegian report to the second review meeting to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The comments, questions and remarks given to Norway's initial national report and Norway's presentation given at the first review meeting have been incorporated in this report. The second report is a full revision of the first report. This report concludes that Norway meets the obligations of the Joint Convention. However, Norwegian authorities will aim for development in the waste management policy and Norway will continue to improve its existing systems to further enhance safety, in line with the aims of the Joint Convention

Plasma, a plant safety monitoring and assessment system for VVER-440 reactors

Energy Technology Data Exchange (ETDEWEB)

Hornaes, A.; Hulsund, J. E. [Institutt for energiteknikk (IFE), OECD Halden Reactor Project, Halden (Norway); Lipcsei, S.; Major, Cs.; Racz, A.; Vegh, J. [KFKI, Atomic Energy Research Institute, Budapest (Hungary); Eiler, J. [Paks, Nuclear Power Plant Ltd, Paks (Hungary)

1999-05-15

The objective with the Plant Safety Monitoring and Assessment System (PLASMA) is to develop an operator support system to support the execution of new symptom-based Emergency Operating Procedures for application in VVER reactors, with the Paks NPP in Hungary as the target plant. Many of the VVER reactors are rewriting their EOPs to comply more with Western standards of symptom-based EOPs. In this connection it is desirable to improve the data validation, information integration and presentation for operators when executing the EOPs. The entry-point to a symptom-oriented procedure is defined by the occurrence of a well-defined reactor operation status, with all its symptoms. However, the application of the EOF benefits from an operator support system, which performs plant status and symptom identification reliably and accurately. The development of the PLASMA system is a joint venture between Institutt for energiteknikk (IFE) and KFKI with the NPP Paks as the target plant. The project has been initiated and partly funded by the Science and Technology Agency (STA), Japan through the OECD NEA assistance program. In Hungary, considerable effort has concentrated on the safety reassessment of the Paks NPP and new EOPs are being written, but no comprehensive Operator Support System (OSS) for plant safety assessment is installed. Some safety parameter display functions are incorporated into diverse operator support systems, but an online 'plant safety monitoring and assessment system' is still missing. The present project comprises designing, constructing, testing and installing such an OSS, which to a great extent could support plant operators in their safety assessment work (author) (ml)

Reconstruction of fiber Bragg grating strain profile used to monitor the stiffness degradation of the adhesive layer in carbon fiber–reinforced plastic single-lap joint

OpenAIRE

Song Chunsheng; Zhang Jiaxiang; Yang Mo; Shang Erwei; Zhang Jinguang

2017-01-01

The adhesive-bonded joint of carbon fiber–reinforced plastic is one of the core components in aircraft structure design. It is an effective guarantee for the safety and reliability of the aerospace aircraft structure to use effective methods for monitoring and early warning of internal failure. In this article, the mapping relation model between the strain profiles of the adherend of the carbon fiber–reinforced plastic single-lap adhesive joint and the stiffness degradation evolution of adhes...

The effects of rock joint geometrical parameters on safety of concrete arch dam abutments

Energy Technology Data Exchange (ETDEWEB)

Yazdani, S.; Yazdani, M.; Joorabchi, A.E. [Tarbiat Modares Univ., Tehran (Iran, Islamic Republic of)

2007-07-01

The International Commission on Large Dams (ICOLD) has stated that foundation failure is the primary cause of dam failure following overtopping. As such, concrete arch dams require strong and stiff abutments. The failure of jointed rock mass at abutments is one of the key mechanisms that may lead to uncontrolled leakage. For that reason, this study investigated the affect of the joint geometrical parameters on the stability of the concrete arch dam abutments. The study also considered the role of joints on the behaviour mechanism of rock mass because it is governed by mechanical and hydraulic properties. The orientation of joints was considered since kinematic conditions are needed for a block to move. The hydromechanical influence of joint apertures on the stability of the foundation was also investigated through nonlinear analyses of different joint orientations and apertures on a hypothetical jointed abutment. Dam abutment safety was estimated by finding the values of maximum sliding and maximum opening and determining the water flow along discontinuities. The values of these 3 indices were derived for different orientations of joints. It was concluded that abutment safety was highly dependent on the geometrical characteristics of joints. 8 refs., 1 tab., 6 figs.

The arrangement of deformation monitoring project and analysis of monitoring data of a hydropower engineering safety monitoring system

Science.gov (United States)

Wang, Wanshun; Chen, Zhuo; Li, Xiuwen

2018-03-01

The safety monitoring is very important in the operation and management of water resources and hydropower projects. It is the important means to understand the dam running status, to ensure the dam safety, to safeguard people’s life and property security, and to make full use of engineering benefits. This paper introduces the arrangement of engineering safety monitoring system based on the example of a water resource control project. The monitoring results of each monitoring project are analyzed intensively to show the operating status of the monitoring system and to provide useful reference for similar projects.

Fatigue Damage Monitoring of a Composite Step Lap Joint Using Distributed Optical Fibre Sensors

Science.gov (United States)

Wong, Leslie; Chowdhury, Nabil; Wang, John; Chiu, Wing Kong; Kodikara, Jayantha

2016-01-01

Over the past few decades, there has been a considerable interest in the use of distributed optical fibre sensors (DOFS) for structural health monitoring of composite structures. In aerospace-related work, health monitoring of the adhesive joints of composites has become more significant, as they can suffer from cracking and delamination, which can have a significant impact on the integrity of the joint. In this paper, a swept-wavelength interferometry (SWI) based DOFS technique is used to monitor the fatigue in a flush step lap joint composite structure. The presented results will show the potential application of distributed optical fibre sensor for damage detection, as well as monitoring the fatigue crack growth along the bondline of a step lap joint composite structure. The results confirmed that a distributed optical fibre sensor is able to enhance the detection of localised damage in a structure. PMID:28773496

Monitoring circuit for reactor safety systems

Science.gov (United States)

Keefe, Donald J.

1976-01-01

The ratio between the output signals of a pair of reactor safety channels is monitored. When ratio falls outside of a predetermined range, it indicates that one or more of the safety channels has malfunctioned.

Health monitoring of 90° bolted joints using fuzzy pattern recognition of ultrasonic signals

International Nuclear Information System (INIS)

Jalalpour, M; El-Osery, A I; Austin, E M; Reda Taha, M M

2014-01-01

Bolted joints are important parts for aerospace structures. However, there is a significant risk associated with assembling bolted joints due to potential human error during the assembly process. Such errors are expensive to find and correct if exposed during environmental testing, yet checking the integrity of individual fasteners after assembly would be a time consuming task. Recent advances in structural health monitoring (SHM) can provide techniques to not only automate this process but also make it reliable. This integrity monitoring requires damage features to be related to physical conditions representing the structural integrity of bolted joints. In this paper an SHM technique using ultrasonic signals and fuzzy pattern recognition to monitor the integrity of 90° bolted joints in aerospace structures is described. The proposed technique is based on normalized fast Fourier transform (NFFT) of transmitted signals and fuzzy pattern recognition. Moreover, experimental observations of a case study on an aluminum 90° bolted joint are presented. We demonstrate the ability of the proposed method to efficiently monitor and indicate bolted joint integrity. (paper)

Health and safety education for joint occupational health and safety committees

Directory of Open Access Journals (Sweden)

Myriam Mahecha Angulo

2015-09-01

Full Text Available Objective: To build a proposal to develop the educational process in health and safety joint committees aimed at safety and health at work (copasst. Methodology: Qualitative, descriptive study in which an in-depth interview to 32 copasst assets was made. Each interview was transcribed and interpreted by applying check with participants, finding meaningful statements, organizing groups of subjects, exhaustive description and validation with participants. The information was placed in the categories planning, organization, development, evaluation and feedback, emerging the following categories: responsible for processes management; planning, place and frequency of educational sessions; topics; format of sessions; involving/ development of sessions; understanding of the issues; applicability to daily life and work environment; applicability to personal/professional life and to the organization. Results: From emerging categories and according to the conceptual framework on adult health education and health and safety for workers, a participatory methodology for the development of educational processes with copasst was built. Conclusions: According to the statement by the members of the copasst, educational processes in health and safety, as they are developed at present, preclude them from achieving necessary competences to perform its functions, thus they are irrelevant.

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report of the Kingdom of the Netherlands

International Nuclear Information System (INIS)

2005-10-01

On 10 March 1999, the Netherlands signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, which was subsequently formally ratified on 26 April 2000 and entered into force on 18 June 2001. The Joint Convention obliges each contracting party to apply widely recognized principles and tools in order to achieve and maintain high standards of safety during management of spent fuel and radioactive waste. The Joint Convention also requires each party to report on the national implementation of these principles to review meetings of the parties to this Convention. This report describes the manner in which the Netherlands is fulfilling its obligations under the Joint Convention

Monitoring circuit for reactor safety systems

International Nuclear Information System (INIS)

Keefe, D.J.

1976-01-01

The ratio between the output signals of a pair of reactor safety channels is monitored. When ratio falls outside of a predetermined range, it indicates that one or more of the safety channels has malfunctioned. 3 claims, 2 figures

Tuning permissiveness of active safety monitors for autonomous systems

OpenAIRE

Masson , Lola; Guiochet , Jérémie; Waeselynck , Hélène; Cabrera , Kalou; Cassel , Sofia; Törngren , Martin

2018-01-01

International audience; Robots and autonomous systems have become a part of our everyday life, therefore guaranteeing their safety is crucial.Among the possible ways to do so, monitoring is widely used, but few methods exist to systematically generate safety rules to implement such monitors. Particularly, building safety monitors that do not constrain excessively the system's ability to perform its tasks is necessary as those systems operate with few human interventions.We propose in this pap...

Risk monitor - a tool for operational safety assessment risk monitor - user's manual

International Nuclear Information System (INIS)

Hari Prasad, M.; Vinod, Gopika; Saraf, R.K.; Ghosh, A.K.

2006-06-01

Probabilistic Safety Assessment has become a key tool as on today to identify and understand Nuclear Power Plant vulnerabilities. As a result of the availability of these PSA studies, there is a desire to use them to enhance plant safety and to operate the nuclear stations in the most efficient manner. Risk Monitor is a PC based tool, which computes the real time safety level and assists plant personnel to manage day-to-day activities. Risk Monitor is a PC based user friendly software tool used for modification and re-analysis of a nuclear Power plant. Operation of Risk Monitor is based on PSA methods for assisting in day to day applications. Risk Monitoring programs can assess the risk profile and are used to optimize the operation of Nuclear Power Plants with respect to a minimum risk level over the operating time. This report presents the background activities of Risk Monitor, its application areas and the step by step procedure for the user.to interact with the software. This software can be used with the PSA model of any Nuclear Power Plant. (author)

Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

International Nuclear Information System (INIS)

2011-11-01

This report contains the national report from Norway to the fourth review meeting of the JointConvention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14-23 May 2012. (Author)

Quality and Safety of Home ICP Monitoring Compared with In-Hospital Monitoring

DEFF Research Database (Denmark)

Andresen, Morten; Juhler, Marianne; Munch, Tina Nørgaard

2012-01-01

Introduction: Intracranial pressure (ICP) monitoring is usually conducted in-hospital using stationary devices. Modern mobile ICP monitoring systems present new monitoring possibilities more closely following the patients' daily life. We reviewed patient safety, quality of technical data...

Introduction to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and Canada's participation

International Nuclear Information System (INIS)

Mecke, J.L.

2011-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) is the first and the only legally binding international instrument to address safety issues concerning the management of spent fuel and radioactive waste on a global scale. It entered into force on June 18, 2001. The Government of Canada strongly supported international efforts to bring into force the Joint Convention and was the second country to ratify it. The Joint Convention is an 'incentive instrument' that is based on peer review (similar in that respect to the Convention on Nuclear Safety) and devised to encourage countries that are Contracting Parties to report and to foster open and frank discussions on the safety of spent fuel and radioactive waste management. Being an incentive convention, it is not designed to mandate Contracting Parties to fulfill its obligation through control and sanction, but it is based on the common objectives of Contracting Parties to achieve and maintain a high level of safety in spent fuel and radioactive waste management, protect individuals, society and the environment from ionizing radiation and prevent accidents and if necessary mitigating the consequences of such accidents. The following paper will provide an introduction to the Joint Convention and provide a summary of Canada's peer review at the most recent Review Meeting which was held on May 11-20, 2009, at the International Atomic Energy Agency (IAEA) headquarters in Vienna, Austria. (author)

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Risoluti, P.

2004-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management (the Joint Convention) is the only legally binding international treaty in the area of radioactive waste management. It was adopted by a Diplomatic Conference in September 1997 and opened for signature on 29 September 1997. The Convention entered into force on 18 June 1998, and to date (September 04) has been signed by 42 States, of which 34 have formally ratified, thus becoming Contracting Parties. The Joint Convention applies to spent fuel and radioactive waste resulting from civilian application. Its principal aim is to achieve and maintain a high degree of safety in their management worldwide. The Convention is an incentive instrument, not designed to ensure fulfillment of obligations through control and sanction, but by a peer pressure. The obligations of the Contracting Parties are mainly based on the international safety standards developed by the IAEA in past decades. The Convention is intended for all countries generating radioactive waste. Therefore it is relevant not only for those using nuclear power, but for any country where application of nuclear energy in medicine, conventional industry and research is currently used. Obligations of Contracting Parties include attending periodic Review Meetings and prepare National Reports for review by the other Contracting Parties. The National Reports should describe how the country is complying with the requirements of the Articles of the Convention. The first such meeting was held at the IAEA headquarters in November 2003. This paper will describe the origin of the Convention, present its content, the expected outcome for the worldwide safety, and the benefits for a country to be part of it

Joint operating agreements - health and safety and employment issues

International Nuclear Information System (INIS)

Molnar, L.F.

1999-01-01

The extent of non-operator exposure to health and safety and other employment liability is considered. Under the terms of the Canadian Association of Petroleum Landman agreements, the designated operator is the sole employer for joint operations. By these terms, the placement of responsibility for employees involved in a joint operation appears clear. It is to rest with the operator alone. As such, one would expect that the non-operator would be free from liabilities arising out of the employment relations of a project. It has been held, in cases of interrelated companies, that an individual can be an employee of more than one company at the same time. Alberta's Occupational Health and Safety Act, as well as the similar Acts in other provinces, impose a hierarchy of duties and obligations not only on employers but also upon contractors, suppliers and workers to ensure that safety is secured. Relevant definitions in the Act state this. An employer of an employee is vicariously liable for torts committed by the employee in the course of his employment. The questions are asked of what happens if a non-operator lends an employee to the operator and the employee tortiously injures a third party, and if the temporary employer, the operator, becomes the employer in the event of vicarious liability. 20 refs

Managing Safety and Operations: The Effect of Joint Management System Practices on Safety and Operational Outcomes.

Science.gov (United States)

Tompa, Emile; Robson, Lynda; Sarnocinska-Hart, Anna; Klassen, Robert; Shevchenko, Anton; Sharma, Sharvani; Hogg-Johnson, Sheilah; Amick, Benjamin C; Johnston, David A; Veltri, Anthony; Pagell, Mark

2016-03-01

The aim of this study was to determine whether management system practices directed at both occupational health and safety (OHS) and operations (joint management system [JMS] practices) result in better outcomes in both areas than in alternative practices. Separate regressions were estimated for OHS and operational outcomes using data from a survey along with administrative records on injuries and illnesses. Organizations with JMS practices had better operational and safety outcomes than organizations without these practices. They had similar OHS outcomes as those with operations-weak practices, and in some cases, better outcomes than organizations with safety-weak practices. They had similar operational outcomes as those with safety-weak practices, and better outcomes than those with operations-weak practices. Safety and operations appear complementary in organizations with JMS practices in that there is no penalty for either safety or operational outcomes.

Joint road safety operations in tunnels and open roads

Science.gov (United States)

Adesiyun, Adewole; Avenoso, Antonio; Dionelis, Kallistratos; Cela, Liljana; Nicodème, Christophe; Goger, Thierry; Polidori, Carlo

2017-09-01

The objective of the ECOROADS project is to overcome the barrier established by the formal interpretation of the two Directives 2008/96/EC and 2004/54/EC, which in practice do not allow the same Road Safety Audits/Inspections to be performed inside tunnels. The projects aims at the establishment of a common enhanced approach to road infrastructure and tunnel safety management by using the concepts and criteria of the Directive 2008/96/CE on road infrastructure safety management and the results of related European Commission (EC) funded projects. ECOROADS has already implemented an analysis of national practices regarding Road Safety Inspections (RSI), two Workshops with the stakeholders, and an exchange of best practices between European tunnel experts and road safety professionals, which led to the definition of common agreed safety procedures. In the second phase of the project, different groups of experts and observers applied the above common procedures by inspecting five European road sections featuring both open roads and tunnels in Belgium, Albania, Germany, Serbia and Former Yugoslav Republic of Macedonia. This paper shows the feedback of the 5 joint safety operations and how they are being used for a set of - recommendations and guidelines for the application of the RSA and RSI concepts within the tunnel safety operations.

Intelligent monitoring-based safety system of massage robot

Institute of Scientific and Technical Information of China (English)

胡宁; 李长胜; 王利峰; 胡磊; 徐晓军; 邹雲鹏; 胡玥; 沈晨

2016-01-01

As an important attribute of robots, safety is involved in each link of the full life cycle of robots, including the design, manufacturing, operation and maintenance. The present study on robot safety is a systematic project. Traditionally, robot safety is defined as follows: robots should not collide with humans, or robots should not harm humans when they collide. Based on this definition of robot safety, researchers have proposed ex ante and ex post safety standards and safety strategies and used the risk index and risk level as the evaluation indexes for safety methods. A massage robot realizes its massage therapy function through applying a rhythmic force on the massage object. Therefore, the traditional definition of safety, safety strategies, and safety realization methods cannot satisfy the function and safety requirements of massage robots. Based on the descriptions of the environment of massage robots and the tasks of massage robots, the present study analyzes the safety requirements of massage robots; analyzes the potential safety dangers of massage robots using the fault tree tool; proposes an error monitoring-based intelligent safety system for massage robots through monitoring and evaluating potential safety danger states, as well as decision making based on potential safety danger states; and verifies the feasibility of the intelligent safety system through an experiment.

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Third review meeting. Questions asked to France and answers

International Nuclear Information System (INIS)

2009-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. For his third report, France presented a document reflecting the viewpoints of the various stakeholders (regulatory authorities and operators). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-stage structure was adopted: first of all a description by the regulatory authority of the regulations, followed by a presentation by the operators of the steps taken to meet the regulations and finally, an analysis by the regulatory authority of the steps taken by the operators. This third report was distributed in October 2008 to all Contracting Parties who asked 213 questions on the French report. France answered each of them in the present document

Multi-field coupled sensing network for health monitoring of composite bolted joint

Science.gov (United States)

Wang, Yishou; Qing, Xinlin; Dong, Liang; Banerjee, Sourav

2016-04-01

Advanced fiber reinforced composite materials are becoming the main structural materials of next generation of aircraft because of their high strength and stiffness to weight ratios, and excellent designability. As key components of large composite structures, joints play important roles to ensure the integrity of the composite structures. However, it is very difficult to analyze the strength and failure modes of composite joints due to their complex nonlinear coupling factors. Therefore, there is a need to monitor, diagnose, evaluate and predict the structure state of composite joints. This paper proposes a multi-field coupled sensing network for health monitoring of composite bolted joints. Major work of this paper includes: 1) The concept of multifunctional sensor layer integrated with eddy current sensors, Rogowski coil and arrayed piezoelectric sensors; 2) Development of the process for integrating the eddy current sensor foil, Rogowski coil and piezoelectric sensor array in multifunctional sensor layer; 3) A new concept of smart composite joint with multifunctional sensing capability. The challenges for building such a structural state sensing system and some solutions to address the challenges are also discussed in the study.

Early warning monitoring system of modular expansion joints based on dynamic behaviour

NARCIS (Netherlands)

Peelen, W.H.A.; Vervuurt, A.H.J.M.; Zuada Coelho, B.E.; Leendertz, H.

2012-01-01

One of the existing modular expansion joints of the Martinus Nijhoff Bridge in the Netherlands was monitored with the purpose of extending its service life for on year until replacement in 2011. Based on an analysis of the failure mechanisms of this (type of) joint, strain gauges were used as

Safety Culture Monitoring: How to Assess Safety Culture in Real Time?

International Nuclear Information System (INIS)

Zronek, B.; Maryska, J.; Treslova, L.

2016-01-01

Do you know what is current level of safety culture in your company? Are you able to follow trend changes? Do you know what your recent issues are? Since safety culture is understood as vital part of nuclear industry daily life, it is crucial to know what the current level is. It is common to perform safety culture survey or ad hoc assessment. This contribution shares Temelin NPP, CEZ approach how to assess safety culture level permanently. Using behavioral related outputs of gap solving system, observation program, dedicated surveys, regulatory assessment, etc., allows creating real time safety culture monitoring without the need to perform any other activities. (author)

Mission and work program of the Joint Committee on Structural Safety

NARCIS (Netherlands)

Vrouwenvelder, A.C.W.M.; Faber, M.H.; Chryssanthopoulos, M.

2003-01-01

The Joint Committee on Structural Safety (JCSS for short) is concerned with fundamental and pre-normative research in the field of Structural Reliability and Risk Assessment, and is directly and indirectly involved in the development of ISO-standards and Eurocodes. The JCSS acts on behalf of five

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Third national report on the implementation of obligations of the Joint Convention

International Nuclear Information System (INIS)

2008-09-01

This report is published in compliance with the Joint Convention and presents the measures implemented by France to comply with each of the obligations defined by this convention. The structure of the report refers to the articles of the Convention. Therefore, after a presentation of the main evolutions since France's previous report, the following themes are addressed: policies and practices, scope of application, inventories and lists, legislative and regulatory system, other general safety provisions, safety of spent fuel management, trans-boundary movement, disused sealed sources, and planned activities to improve safety

Sweden's first national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2003-01-01

This report is issued according to Article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Sweden signed the Joint Convention September 29, 1997 and the Joint Convention entered into force on June 18, 2001. The areas covered by the Joint Convention have been incorporated in the Swedish system for spent fuel and radioactive waste management for a long time. The Swedish Government considered at the time of signing of the Joint Convention that the safety philosophy, legislation and the safety work conducted by the licensees and the authorities in Sweden complied with the obligations of the Convention. This is confirmed in the present report. The Swedish Government directed the Swedish Nuclear Power Inspectorate (SKI) to prepare this report in co-operation with the Swedish Radiation Protection Authority (SSI). A working group of five persons, with representatives from SKI, SSI and the Swedish Nuclear Fuel and Waste Management Co. (SKB), has prepared this report. The report has been discussed in the boards of SKI and SSI. The Swedish Government adopted the report in April 2003. Section A of this report provides an overview of the Swedish nuclear waste programme, including a brief historical review, in order to give the reader a background to the current programme for the management of spent fuel and radioactive waste. Sections B to J provide information on which the conclusions are drawn about the compliance with the obligations of the Joint Convention. By necessity this information is rather brief and strongly focused on those aspects which are addressed in the articles. Too many details and additional information would over-load the report and make the review process difficult. The goal has been to provide enough details to make the Swedish practices understandable. Data that might be missing will be added on request as a part of the review process. Article 32 of the Joint Convention calls for a self

Risk-based reconfiguration of safety monitoring system using dynamic Bayesian network

International Nuclear Information System (INIS)

Kohda, Takehisa; Cui Weimin

2007-01-01

To prevent an abnormal event from leading to an accident, the role of its safety monitoring system is very important. The safety monitoring system detects symptoms of an abnormal event to mitigate its effect at its early stage. As the operation time passes by, the sensor reliability decreases, which implies that the decision criteria of the safety monitoring system should be modified depending on the sensor reliability as well as the system reliability. This paper presents a framework for the decision criteria (or diagnosis logic) of the safety monitoring system. The logic can be dynamically modified based on sensor output data monitored at regular intervals to minimize the expected loss caused by two types of safety monitoring system failure events: failed-dangerous (FD) and failed-safe (FS). The former corresponds to no response under an abnormal system condition, while the latter implies a spurious activation under a normal system condition. Dynamic Bayesian network theory can be applied to modeling the entire system behavior composed of the system and its safety monitoring system. Using the estimated state probabilities, the optimal decision criterion is given to obtain the optimal diagnosis logic. An illustrative example of a three-sensor system shows the merits and characteristics of the proposed method, where the reasonable interpretation of sensor data can be obtained

Monitoring and reviewing research reactor safety in Australia

International Nuclear Information System (INIS)

Cairns, R.C.; Greenslade, G.K.

1990-01-01

Th research reactors operated by the Australian Nuclear Science and Technology Organization (ANSTO) comprise the 10 MW reactor HIFAR and the 100 kW reactor Moata. Although there are no power reactors in Australia the problems and issues of public concern which arise in the operation of research reactors are similar to those of power reactors although on a smaller scale. The need for independent safety surveillance has been recognized by the Australian Government and the ANSTO Act, 1987, required the Board of ANSTO to establish a Nuclear Safety Bureau (NSB) with responsibility to the Minister for monitoring and reviewing the safety of nuclear plant operated by ANSTO. The Executive Director of ANSTO operates HIFAR subject to compliance with requirements and arrangements contained in a formal Authorization from the Board of ANSTO. A Ministerial Direction to the Board of ANSTO requires the NSB to report to him, on a quarterly basis, matters relating to its functions of monitoring and reviewing the safety of ANSTO's nuclear plant. Experience has shown that the Authorization provides a suitable framework for the operational requirements and arrangements to be organised in a disciplined and effective manner, and also provides a basis for audits by the NSB by which compliance with the Board's safety requirements are monitored. Examples of the way in which the NSB undertakes its monitoring and reviewing role are given. Moata, which has a much lower operating power level and fission product inventory than HIFAR, has not been subject to a formal Authorization to date but one is under preparation

Monitoring individual and joint action outcomes in duet music performance

DEFF Research Database (Denmark)

Loehr, Janeen; Kourtis, Dimitrios; Vesper, Cordula

2013-01-01

We investigated whether people monitor the outcomes of their own and their partners’ individual actions as well as the outcome of their combined actions when performing joint actions together. Pairs of pianists memorized both parts of a piano duet. Each pianist then performed one part while their...

78 FR 12065 - Patient Safety Organizations: Delisting for Cause for Independent Data Safety Monitoring, Inc.

Science.gov (United States)

2013-02-21

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Safety Monitoring, Inc. due to its failure to correct a deficiency. The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the listing of PSOs, which are entities or component...

A sensor monitoring system for telemedicine, safety and security applications

Science.gov (United States)

Vlissidis, Nikolaos; Leonidas, Filippos; Giovanis, Christos; Marinos, Dimitrios; Aidinis, Konstantinos; Vassilopoulos, Christos; Pagiatakis, Gerasimos; Schmitt, Nikolaus; Pistner, Thomas; Klaue, Jirka

2017-02-01

A sensor system capable of medical, safety and security monitoring in avionic and other environments (e.g. homes) is examined. For application inside an aircraft cabin, the system relies on an optical cellular network that connects each seat to a server and uses a set of database applications to process data related to passengers' health, safety and security status. Health monitoring typically encompasses electrocardiogram, pulse oximetry and blood pressure, body temperature and respiration rate while safety and security monitoring is related to the standard flight attendance duties, such as cabin preparation for take-off, landing, flight in regions of turbulence, etc. In contrast to previous related works, this article focuses on the system's modules (medical and safety sensors and associated hardware), the database applications used for the overall control of the monitoring function and the potential use of the system for security applications. Further tests involving medical, safety and security sensing performed in an real A340 mock-up set-up are also described and reference is made to the possible use of the sensing system in alternative environments and applications, such as health monitoring within other means of transport (e.g. trains or small passenger sea vessels) as well as for remotely located home users, over a wired Ethernet network or the Internet.

Joint hierarchical Gaussian process model with application to personalized prediction in medical monitoring.

Science.gov (United States)

Duan, Leo L; Wang, Xia; Clancy, John P; Szczesniak, Rhonda D

2018-01-01

A two-level Gaussian process (GP) joint model is proposed to improve personalized prediction of medical monitoring data. The proposed model is applied to jointly analyze multiple longitudinal biomedical outcomes, including continuous measurements and binary outcomes, to achieve better prediction in disease progression. At the population level of the hierarchy, two independent GPs are used to capture the nonlinear trends in both the continuous biomedical marker and the binary outcome, respectively; at the individual level, a third GP, which is shared by the longitudinal measurement model and the longitudinal binary model, induces the correlation between these two model components and strengthens information borrowing across individuals. The proposed model is particularly advantageous in personalized prediction. It is applied to the motivating clinical data on cystic fibrosis disease progression, for which lung function measurements and onset of acute respiratory events are monitored jointly throughout each patient's clinical course. The results from both the simulation studies and the cystic fibrosis data application suggest that the inclusion of the shared individual-level GPs under the joint model framework leads to important improvements in personalized disease progression prediction.

Optical Fiber Sensors For Monitoring Joint Articulation And Chest Expansion Of A Human Body

Science.gov (United States)

Muhs, Jeffrey D.; Allison, Stephen W.

1997-12-23

Fiber-optic sensors employing optical fibers of elastomeric material are incorporated in devices adapted to be worn by human beings in joint and chest regions for the purpose of monitoring and measuring the extent of joint articulation and chest expansion especially with respect to time.

Benefits of joint audits of service company and operator personnel

International Nuclear Information System (INIS)

Ritchie, R.D.

1991-01-01

Companies operating in the petroleum industry are showing an increasing collective awareness of safety and environmental issues. The objective of management in any organization is to identify potential hazards and develop and implement an action plant to eliminate these hazards. Joint audits between operating companies and service companies have proved an effective means of developing an objective and realistic safety awareness program. Joint audits, unlike external audits, enable both companies to develop, implement and monitor a meaningful safety policy based on factual information. The paper describes the planning, execution and follow up of an in-depth joint audit. Analysis of the audit results generated action plans to correct areas in need of improvement for both the operating and service companies. Of these areas, most could be corrected and resolved within three months while the remainder were targeted for remedial action to be completed within one year. The paper provides a thorough set of guidelines for all stages of a successful joint audit and illustrates, with examples, the operational improvements to be gained from such operator/service-company cooperation

The Cost of Jointness: Insights from Environmental Monitoring Systems in Low-Earth Orbit

Energy Technology Data Exchange (ETDEWEB)

Dwyer, Morgan Maeve [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-09-01

This report summarizes the results of doctoral research that explored the cost impact of acquiring complex government systems jointly. The report begins by reviewing recent evidence that suggests that joint programs experience greater cost growth than non-joint programs. It continues by proposing an alternative approach for studying cost growth on government acquisition programs and demonstrates the utility of this approach by applying it to study the cost of jointness on three past programs that developed environmental monitoring systems for low-Earth orbit. Ultimately, the report concludes that joint programs' costs grow when the collaborating government agencies take action to retain or regain their autonomy. The report provides detailed qualitative and quantitative data in support of this conclusion and generalizes its findings to other joint programs that were not explicitly studied here. Finally, it concludes by presenting a quantitative model that assesses the cost impacts of jointness and by demonstrating how government agencies can more effectively architect joint programs in the future.

The announcement of the Ministry of Foreign Affairs of the Slovak Republic about Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management

International Nuclear Information System (INIS)

2002-01-01

The Ministry of Foreign Affairs of the Slovak Republic amends that in 30 September 1997 in Vienna was undersigned the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. This Joint Convention came into force on June 18, 2001

Temelin safety monitor

International Nuclear Information System (INIS)

Mlady, O.

2000-01-01

Temelin NPP is a WWER-1000/320 two unit plant under construction, originally designed according to the standards of the former Soviet Union. After a series of reviews in the 80s, a decision was taken to upgrade the design of Temelin, including the supply of fuel and instrumentation and instrumentation and control system (I and C). Details on the current design and other related safety matters were presented to the nuclear community in a meeting organized by the IAEA in November 1994. Based upon recommendations of IAEA OSART missions, post TMI requirements and Temelin Risk Audit recommendations it was decided to perform a Probabilistic Safety Assessment within the Temelin PSA Project. The general purpose of this project was to perform systematic examination of the Temelin Unit 1 NPP for severe accident vulnerabilities by performance of a Level 1 and 2 PSA study. In addition to the completion of Temelin documented living PSA model, the decision was to develop and implement a PSA based software tool able to analyze real and scheduled plant conditions for determining the risk impact of plant configurations and on-line maintenance activities. This paper provides an overview of the key features of the Temelin Safety Monitor, describes its development activities and its current status and intended use at Temelin NPP for PSA applications. (author)

Joint sampling programme-Verification of data obtained in environmental monitoring

Energy Technology Data Exchange (ETDEWEB)

Lauria, D.C. [Instituto de Radioprotecao e Dosimetria, Comissao Nacional de Energia Nuclear, Av. Salvador Allende s/no., CEP 22780-160, Rio de Janeiro, RJ (Brazil)], E-mail: dejanira@ird.gov.br; Martins, N.S.F.; Vasconcellos, M.L.H.; Zenaro, R.; Peres, S.S.; Pires do Rio, M.A. [Instituto de Radioprotecao e Dosimetria, Comissao Nacional de Energia Nuclear, Av. Salvador Allende s/no., CEP 22780-160, Rio de Janeiro, RJ (Brazil)

2008-11-15

The objective of the Environmental Radiological Monitoring Control programme carried out by the Institute of Radiation Protection and Dosimetry (IRD) in Brazil is to verify the licensee's compliance with the requirements for environmental monitoring of Brazilian facilities. The Joint Sampling Programme (JSP) is just one part of the control programme. In order to verify that the data reported by the licensees is representative and legitimate, this programme verifies sampling procedures, accuracy and precision of the data and the changes in the environmental conditions. This paper discusses the main findings of this programme that allowed IRD to optimize its available resources to control the monitoring of the eight facilities in Brazil.

75 FR 17417 - Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management...

Science.gov (United States)

2010-04-06

...] Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory... Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory Committee. This meeting was... Drug Safety and Risk Management Advisory Committee would be held on May 12, 2010. On page 10490, in the...

Multi-dimensional database design and implementation of dam safety monitoring system

Directory of Open Access Journals (Sweden)

Zhao Erfeng

2008-09-01

Full Text Available To improve the effectiveness of dam safety monitoring database systems, the development process of a multi-dimensional conceptual data model was analyzed and a logic design was achieved in multi-dimensional database mode. The optimal data model was confirmed by identifying data objects, defining relations and reviewing entities. The conversion of relations among entities to external keys and entities and physical attributes to tables and fields was interpreted completely. On this basis, a multi-dimensional database that reflects the management and analysis of a dam safety monitoring system on monitoring data information has been established, for which factual tables and dimensional tables have been designed. Finally, based on service design and user interface design, the dam safety monitoring system has been developed with Delphi as the development tool. This development project shows that the multi-dimensional database can simplify the development process and minimize hidden dangers in the database structure design. It is superior to other dam safety monitoring system development models and can provide a new research direction for system developers.

The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. An instrument to achieve a global safety

International Nuclear Information System (INIS)

Risoluti, P.

2006-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management (the Joint Convention) is the first legally binding international treaty in the area of radioactive material management. It was adopted by a Diplomatic Conference in September 1997 and opened for signature on 29 September 1997. The Convention entered into force on 18 June 1998, and to date (May 2006) has been ratified by 41 countries. The Joint Convention applies to spent fuel and radioactive waste resulting from civilian application. Its principal aim is to achieve and maintain a high degree of safety in their management worldwide. The Convention is an incentive instrument, not designed to ensure fulfilment of obligations through control and sanction, but by a volunteer peer review mechanism. The obligations of the Contracting Parties are mainly based on the international safety standards developed by the IAEA in past decades. The Convention is of interest of all countries generating radioactive waste. Therefore it is relevant not only for those using nuclear power, but for any country where application of nuclear energy in education, agriculture, medicine and industry is currently used. Obligations of Contracting Parties include attending a Review Meeting held every three years and prepare National Reports for review by the other Contracting Parties. In the National Reports basic information on inventory and facilities for management of radioactive materials has to be provided. Countries with small nuclear power and/or research programs or countries having radioactive materials only from nuclear application on medicine, agriculture or conventional industry, can benefit from the exchange of information and the technical knowledge gained by the reporting procedure set up by the Convention. The second Review Meeting is to be held at IAEA headquarters from 15 to 26 May 2006. This paper presents the objectives and the implementation status of the Convention, the

The Ageing Effect of Mechanical Joints on the Tyre/Joint Noises Monitored by a Control Vehicle Method without Traffic Disturbance

Directory of Open Access Journals (Sweden)

C. K. Wong

2013-01-01

Full Text Available This paper studies the ageing effect of mechanical joints reflecting from the tyre/joint impacting noise by measuring the vehicle structure-borne noise change. Field data is collected applying two measurement methods suitable for newly installed and existing old expansion joints. The measurement methodology is improved by designing and applying a trailer for equipment installation. The main advantage of this method is not to disturb existing traffic by lane closure for measurement. Field measurements were conducted regularly for a study period up to 16 months after new joint replacement to monitor the variation of the structure-borne noise change inside a test vehicle while passing through mechanical joints. Empirical relationship is developed based on the field data of the roadside airborne noise change and the vehicle structure-borne noise change. The roadside tyre/joint noises could be converted using calibrated empirical formula. Key result findings include the following. (1 The vehicle structure-borne noise change is found smallest during the 3rd–6th months even lower than that measured when a new joint is installed. The structure-borne noise change then keeps increasing afterwards till the end of the study period. (2 Similar observations are found in all study cases incorporating various mechanical joint types and test vehicle types.

Crude versus case-mix-adjusted control charts for safety monitoring in thyroid surgery.

Science.gov (United States)

Duclos, Antoine; Voirin, Nicolas; Touzet, Sandrine; Soardo, Pietro; Schott, Anne-Marie; Colin, Cyrille; Peix, Jean-Louis; Lifante, Jean-Christophe

2010-12-01

Patient-safety monitoring based on health-outcome indicators can lead to misinterpretation of changes in case mix. This study aimed to compare the detection of indicator variations between crude and case-mix-adjusted control charts using data from thyroid surgeries. The study population included each patient who underwent thyroid surgery in a teaching hospital from January 2006 to May 2008. Patient safety was monitored according to two indicators, which are immediately recognisable postoperative complications: recurrent laryngeal nerve palsy and hypocalcaemia. Each indicator was plotted monthly on a p-control chart using exact limits. The weighted κ statistic was calculated to measure the agreement between crude and case-mix-adjusted control charts. We evaluated the outcomes of 1405 thyroidectomies. The overall proportions of immediate recurrent laryngeal nerve palsy and hypocalcaemia were 7.4% and 20.5%, respectively. The proportion of agreement in the detection of indicator variations between the crude and case-mix-adjusted p-charts was 95% (95% CI 85% to 99%). The strength of the agreement was κ = 0.76 (95% CI 0.54 to 0.98). The single special cause of variation that occurred was only detected by the case-mix-adjusted p-chart. There was good agreement in the detection of indicator variations between crude and case-mix-adjusted p-charts. The joint use of crude and adjusted charts seems to be a reasonable approach to increase the accuracy of interpretation of variations in outcome indicators.

Assessing Drinking Water Quality and Water Safety Management in Sub-Saharan Africa Using Regulated Monitoring Data.

Science.gov (United States)

Kumpel, Emily; Peletz, Rachel; Bonham, Mateyo; Khush, Ranjiv

2016-10-18

Universal access to safe drinking water is prioritized in the post-2015 Sustainable Development Goals. Collecting reliable and actionable water quality information in low-resource settings, however, is challenging, and little is known about the correspondence between water quality data collected by local monitoring agencies and global frameworks for water safety. Using 42 926 microbial water quality test results from 32 surveillance agencies and water suppliers in seven sub-Saharan African countries, we determined the degree to which water sources were monitored, how water quality varied by source type, and institutional responses to results. Sixty-four percent of the water samples were collected from piped supplies, although the majority of Africans rely on nonpiped sources. Piped supplies had the lowest levels of fecal indicator bacteria (FIB) compared to any other source type: only 4% of samples of water piped to plots and 2% of samples from water piped to public taps/standpipes were positive for FIB (n = 14 948 and n = 12 278, respectively). Among other types of improved sources, samples from harvested rainwater and boreholes were less often positive for FIB (22%, n = 167 and 31%, n = 3329, respectively) than protected springs or protected dug wells (39%, n = 472 and 65%, n = 505). When data from different settings were aggregated, the FIB levels in different source types broadly reflected the source-type water safety framework used by the Joint Monitoring Programme. However, the insufficient testing of nonpiped sources relative to their use indicates important gaps in current assessments. Our results emphasize the importance of local data collection for water safety management and measurement of progress toward universal safe drinking water access.

Effect of joint mechanism on vehicle redirectional capability of water-filled road safety barrier systems.

Science.gov (United States)

Thiyahuddin, M I; Thambiratnam, D P; Gu, Y T

2014-10-01

Portable water-filled barriers (PWFBs) are roadside appurtenances that prevent vehicles from penetrating into temporary construction zones on roadways. PWFBs are required to satisfy the strict regulations for vehicle re-direction in tests. However, many of the current PWFBs fail to re-direct the vehicle at high speeds due to the inability of the joints to provide appropriate stiffness. The joint mechanism hence plays a crucial role in the performance of a PWFB system at high speed impacts. This paper investigates the desired features of the joint mechanism in a PWFB system that can re-direct vehicles at high speeds, while limiting the lateral displacement to acceptable limits. A rectangular "wall" representative of a 30m long barrier system was modeled and a novel method of joining adjacent road barriers was introduced through appropriate pin-joint connections. The impact response of the barrier "wall" and the vehicle was obtained and the results show that a rotational stiffness of 3000kNm/rad at the joints seems to provide the desired features of the PWFB system to re-direct impacting vehicles and restrict the lateral deflection. These research findings will be useful to safety engineers and road barrier designers in developing a new generation of PWFBs for increased road safety. Copyright © 2014 Elsevier Ltd. All rights reserved.

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. 2005

International Nuclear Information System (INIS)

Hekel, P.; Ivan, J.; Lukacovic, K.; Parimucha, F.; Suss, J; Tomek, J.; Jurina, V.; Kobzova, D.; Konecny, L.; Homola, J.; Zavazanova, A.; Metke, E.; Turner, M.; Vaclav, J.; Ziakova, M.; Pospisil, M.; Petrik, T.

2005-09-01

The National Report (Compiled in terms of the Joint Convention - September 2005) contains information how each of the obligations of the Joint Convention have been implemented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) and other Slovak organisations are presented. These activities are reported under the headings: (A) Introduction; (B) Spent fuel and radioactive waste management; C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of RAW management; (I) Transboundary movement of SF and RAW; (J) Disused sealed sources; (K) planned activiries to improve safety; (L) Annexes

76 FR 59142 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

Science.gov (United States)

2011-09-23

...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the...., [[Page 59143

Reconstruction of fiber Bragg grating strain profile used to monitor the stiffness degradation of the adhesive layer in carbon fiber–reinforced plastic single-lap joint

Directory of Open Access Journals (Sweden)

Song Chunsheng

2017-01-01

Full Text Available The adhesive-bonded joint of carbon fiber–reinforced plastic is one of the core components in aircraft structure design. It is an effective guarantee for the safety and reliability of the aerospace aircraft structure to use effective methods for monitoring and early warning of internal failure. In this article, the mapping relation model between the strain profiles of the adherend of the carbon fiber–reinforced plastic single-lap adhesive joint and the stiffness degradation evolution of adhesive layer was achieved by finite element software ABAQUS. The fiber Bragg grating was embedded in the adherend between the first and second layers at the end of the adhesive layer to calculate the reflection spectrum of fiber Bragg grating sensor region with improved T-matrix method for reconstruction of the adherend strain profile of fiber Bragg grating sensing area with the help of genetic algorithm. According to the reconstruction results, the maximum error between the ideal and reconstructed strain profile under different tension loads did not exceed 7.43%, showing a good coincidence degree. The monitoring method of the stiffness degradation evolution of adhesive layer of the carbon fiber–reinforced plastic single-lap joint based on the reconstruction of the adherend strain profile of fiber Bragg grating sensing area thus was figured out.

The evolution and future direction of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Siraky, Gabriela

2008-01-01

Full text: The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, namely the Joint Convention, had been established in 1997. The objective of the Convention is to achieve and maintain a high level of safety worldwide in that fields to ensure that there are effective defenses against potential hazards so that individuals, society and the environment are protected from the harmful effects of ionizing radiation and to prevent accidents with radiological consequences and to mitigate their consequences. The Parties to the Convention intend to achieve this objective by international cooperation, peer reviews of each other's performance, assistance when needed for states with less developed programmes and capabilities and the use of internationally accepted standards of safety. The Joint Convention is rooted in the discussions held previously to the establishment of the Convention of the Nuclear Safety that had taken place in the period 1993-1994. The idea of a Convention on the Safety of waste management evolved since then, getting its final status in November 1997 after seven meetings of a specially appointed working group of outstanding specialists on the subject. After that, it was needed three years more until the number of the ratifying States, that then became Contracting Parties, to get the condition that let the Convention to enter into force: ninety days after the date of deposit with the Depository of the twenty-fifth instrument of ratification, acceptance or approval, including the instruments of fifteen States having an operational nuclear power plant. The First Review Meeting was held three years after it entered into force, in November 2003, with the attendance of 33 Parties that presented their National Reports. The second review meeting was held in May 2006. Forty-one Contracting Parties participated in the Second Review Meeting. There is then, a constant evolution in the number of Contracting Parties

76 FR 63929 - Joint Meeting of the Drug Safety and Risk Management Advisory Committee and the Dermatologic and...

Science.gov (United States)

2011-10-14

...] Joint Meeting of the Drug Safety and Risk Management Advisory Committee and the Dermatologic and... Administration (FDA). The meeting will be open to the public. Name of Committees: Drug Safety and Risk Management... Safe Use (ETASU) before its Drug Safety and Risk Management Advisory Committee (DSaRM). On December 1...

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. France's answers to questions and comments received from other Contracting Parties on its second report for the JC

International Nuclear Information System (INIS)

2009-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. For his second report, France presented a document reflecting the viewpoints of the various stakeholders (regulatory authorities and operators). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-stage structure was adopted: first of all a description by the regulatory authority of the regulations, followed by a presentation by the operators of the steps taken to meet the regulations and finally, an analysis by the regulatory authority of the steps taken by the operators. France received questions and comments from the other contracting parties of the joint convention and answered them in the present document

Partial safety factor calibration from stochastic finite element computation of welded joint with random geometries

International Nuclear Information System (INIS)

Schoefs, Franck; Chevreuil, Mathilde; Pasqualini, Olivier; Cazuguel, Mikaël

2016-01-01

Welded joints are used in various structures and infrastructures like bridges, ships and offshore structures, and are submitted to cyclic stresses. Their fatigue behaviour is an industrial key issue to deal with and still offers original research subjects. One of the available methods relies on the computing of the stress concentration factor. Even if some studies were previously driven to evaluate this factor onto some cases of welded structures, the shape of the weld joint is generally idealized through a deterministic parametric geometry. Previous experimental works however have shown that this shape plays a key role in the lifetime assessment. We propose in this paper a methodology for computing the stress concentration factor in presence of random geometries of welded joints. In view to make the results available by engineers, this method merges stochastic computation and semi-probabilistic analysis by computing partial safety factors with a dedicated method. - Highlights: • Numerical computation of stress concentration factor with random geometry of weld. • Real data are used for probabilistic modelling. • Identification of partial safety factor from SFEM computation in case of random geometries.

A structural health monitoring fastener for tracking fatigue crack growth in bolted metallic joints

Science.gov (United States)

Rakow, Alexi Schroder

Fatigue cracks initiating at fastener hole locations in metallic components are among the most common form of airframe damage. The fastener hole site has been surveyed as the second leading initiation site for fatigue related accidents of fixed wing aircraft. Current methods for inspecting airframes for these cracks are manual, whereby inspectors rely on non-destructive inspection equipment or hand-held probes to scan over areas of a structure. Use of this equipment often demands disassembly of the vehicle to search appropriate hole locations for cracks, which elevates the complexity and cost of these maintenance inspections. Improved reliability, safety, and reduced cost of such maintenance can be realized by the permanent integration of sensors with a structure to detect this damage. Such an integrated system of sensors would form a structural health monitoring (SHM) system. In this study, an Additive, Interleaved, Multi-layer Electromagnetic (AIME) sensor was developed and integrated with the shank of a fastener to form a SHM Fastener, a new SHM technology targeted at detection of fastener hole cracks. The major advantages of the SHM Fastener are its installation, which does not require joint layer disassembly, its capability to detect inner layer cracks, and its capability to operate in a continuous autonomous mode. Two methods for fabricating the proposed SHM Fastener were studied. The first option consisted of a thin flexible printed circuit film that was bonded around a thin metallic sleeve placed around the fastener shank. The second option consisted of coating sensor materials directly to the shank of a part in an effort to increase the durability of the sensor under severe loading conditions. Both analytical and numerical models were developed to characterize the capability of the sensors and provide a design tool for the sensor layout. A diagnostic technique for crack growth monitoring was developed to complete the SHM system, which consists of the

Safety performance monitoring of autonomous marine systems

International Nuclear Information System (INIS)

Thieme, Christoph A.; Utne, Ingrid B.

2017-01-01

The marine environment is vast, harsh, and challenging. Unanticipated faults and events might lead to loss of vessels, transported goods, collected scientific data, and business reputation. Hence, systems have to be in place that monitor the safety performance of operation and indicate if it drifts into an intolerable safety level. This article proposes a process for developing safety indicators for the operation of autonomous marine systems (AMS). The condition of safety barriers and resilience engineering form the basis for the development of safety indicators, synthesizing and further adjusting the dual assurance and the resilience based early warning indicator (REWI) approaches. The article locates the process for developing safety indicators in the system life cycle emphasizing a timely implementation of the safety indicators. The resulting safety indicators reflect safety in AMS operation and can assist in planning of operations, in daily operational decision-making, and identification of improvements. Operation of an autonomous underwater vehicle (AUV) exemplifies the process for developing safety indicators and their implementation. The case study shows that the proposed process leads to a comprehensive set of safety indicators. It is expected that application of the resulting safety indicators consequently will contribute to safer operation of current and future AMS. - Highlights: • Process for developing safety indicators for autonomous marine systems. • Safety indicators based on safety barriers and resilience thinking. • Location of the development process in the system lifecycle. • Case study on AUV demonstrating applicability of the process.

Performance Monitoring for Nuclear Safety Related Instrumentation at PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2015-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on performance monitoring for nuclear safety related instrumentation in TRIGA PUSPATI Reactor (RTP) of based on various parameter of reactor safety instrument channel such as log power, linear power, Fuel temperature, coolant temperature will take into consideration. Methodology of performance on estimation and monitoring is to evaluate and analysis of reactor parameters which is important of reactor safety and control. And also to estimate power measurement, differential of log and linear power and fuel temperature during reactor start-up, operation and shutdown .This study also focus on neutron power fluctuation from fission chamber during reactor start-up and operation. This work will present result of performance monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that performance of nuclear safety related instrumentation will improved the reactor control and safety parameter during reactor start-up, operation and shutdown. (author)

Safety valve opening and closing operation monitor

International Nuclear Information System (INIS)

Kodama, Kunio; Takeshima, Ikuo; Takahashi, Kiyokazu.

1981-01-01

Purpose: To enable the detection of the closing of a safety valve when the internal pressure in a BWR type reactor is a value which will close the safety valve, by inputting signals from a pressure detecting device mounted directly at a reactor vessel and a safety valve discharge pressure detecting device to an AND logic circuit. Constitution: A safety valve monitor is formed of a pressure switch mounted at a reactor pressure vessel, a pressure switch mounted at the exhaust pipe of the escape safety valve and a logic circuit and the lide. When the input pressure of the safety valve is raised so that the valve and the pressure switch mounted at the exhaust pipe are operated, an alarm is indicated, and the operation of the pressure switch mounted at a pressure vessel is eliminated. If the safety valve is not reclosed when the vessel pressure is decreased lower than the pressure at which it is to be reclosed after the safety valve is operated, an alarm is generated by the logic circuit since both the pressure switches are operated. (Sekiya, K.)

Joint probability safety assessment for NPP defense infrastructure against extreme external natural hazards

International Nuclear Information System (INIS)

Guilin, L.; Defu, L.; Huajun, L.; Fengqing, W.; Tao, Z.

2012-01-01

With the increasing tendency of natural hazards, the typhoon, hurricane and tropical Cyclone induced surge, wave, precipitation, flood and wind as extreme external loads menacing Nuclear Power Plants (NPP) in coastal and inland provinces of China. For all of planned, designed And constructed NPP the National Nuclear Safety Administration of China and IAEA recommended Probable Maximum Hurricane /Typhoon/(PMH/T), Probable Maximum Storm Surge (PMSS), Probable Maximum Flood (PMF), Design Basis Flood (DBF) as safety regulations for NPP defense infrastructures. This paper discusses the joint probability analysis of simultaneous occurrence typhoon induced extreme external hazards and compare with IAEA 2006-2009 recommended safety regulation design criteria for some NPP defense infrastructures along China coast. (authors)

Automated discovery of safety and efficacy concerns for joint & muscle pain relief treatments from online reviews.

Science.gov (United States)

Adams, David Z; Gruss, Richard; Abrahams, Alan S

2017-04-01

Product issues can cost companies millions in lawsuits and have devastating effects on a firm's sales, image and goodwill, especially in the era of social media. The ability for a system to detect the presence of safety and efficacy (S&E) concerns early on could not only protect consumers from injuries due to safety hazards, but could also mitigate financial damage to the manufacturer. Prior studies in the field of automated defect discovery have found industry-specific techniques appropriate to the automotive, consumer electronics, home appliance, and toy industries, but have not investigated pain relief medicines and medical devices. In this study, we focus specifically on automated discovery of S&E concerns in over-the-counter (OTC) joint and muscle pain relief remedies and devices. We select a dataset of over 32,000 records for three categories of Joint & Muscle Pain Relief treatments from Amazon's online product reviews, and train "smoke word" dictionaries which we use to score holdout reviews, for the presence of safety and efficacy issues. We also score using conventional sentiment analysis techniques. Compared to traditional sentiment analysis techniques, we found that smoke term dictionaries were better suited to detect product concerns from online consumer reviews, and significantly outperformed the sentiment analysis techniques in uncovering both efficacy and safety concerns, across all product subcategories. Our research can be applied to the healthcare and pharmaceutical industry in order to detect safety and efficacy concerns, reducing risks that consumers face using these products. These findings can be highly beneficial to improving quality assurance and management in joint and muscle pain relief. Copyright © 2017 Elsevier B.V. All rights reserved.

Environmental and Source Monitoring for Purposes of Radiation Protection. Safety Guide (Spanish ed.)

International Nuclear Information System (INIS)

2010-01-01

The purpose of this Safety Guide is to provide international guidance, coherent with contemporary radiation protection principles and IAEA safety requirements, on the strategy of monitoring in relation to: (a) control of radionuclide discharges under practice conditions, and (b) intervention, such as in cases of nuclear or radiological emergencies or past contamination of areas with long lived radionuclides. Three categories of monitoring are discussed: monitoring at the source of the discharge (source monitoring), monitoring in the environment (environmental monitoring) and monitoring of individual exposure in emergencies (individual monitoring). The Safety Guide also provides general guidance on assessment of the doses to critical groups of the population due to the presence of radioactive materials or radiation fields in the environment both from routine operation of nuclear and other related facilities (practice) and from nuclear or radiological emergencies and past contamination of areas with long lived radionuclides (intervention). The dose assessments are based on the results of source monitoring, environmental monitoring, individual monitoring or their combinations. This Safety Guide is primarily intended for use by national regulatory bodies and other agencies involved in national systems of radiation monitoring, as well as by operators of nuclear installations and other facilities where natural or human made radionuclides are treated and monitored. Contents: 1. Introduction; 2. Meeting regulatory requirements for monitoring in practices and interventions; 3. Responsibilities for monitoring; 4. Generic aspects of monitoring programmes; 5. Programmes for monitoring in practices and interventions; 6. Technical conditions for monitoring procedures; 7. Considerations in dose assessment; 8. Interpretation of monitoring results; 9. Quality assurance; 10. Recording of results; 11. Education and training; Glossary.

WARMS - a continuous on-line environmental and emergency radiation monitoring system

International Nuclear Information System (INIS)

Ramsden, D.

1984-01-01

The Winfrith Airborne Release Monitoring System (WARMS) is used to monitor the environment around the Winfrith reactor site. It operates continuously monitoring the background radiation at 16 outstations and can provide rapid information should an accidental release occur. WARMS was developed jointly by the Radiological Safety Division and the Control and Instrumentation Division at Winfrith in association with the Safety and Reliability Directorate at Culcheth which developed the software. The system became operational in the autumn of 1983 and has since demonstrated a high degree of reliability and effectiveness. (author)

Potential of acoustic monitoring for safety assessment of primary system

International Nuclear Information System (INIS)

Olma, B.J.

1997-01-01

Safety assessment of the primary system and its components with respect to their mechanical integrity is increasingly supported by acoustic signature analysis during power operation of the plants. Acoustic signals of Loose Parts Monitoring System sensors are continuously monitored by dedicated digital systems for signal bursts associated with metallic impacts. Several years of ISTec/GRS experience and the practical use of its digital systems MEDEA and RAMSES have shown that acoustic monitoring is very successful for detecting component failures at an early stage. Advanced powerful tools for classification and acoustic evaluation of burst signals have recently been realized. The paper presents diagnosis experiences of BWR's and PWR's safety assessment. (author). 7 refs, 8 figs

Microseismic monitoring of columnar jointed basalt fracture activity: a trial at the Baihetan Hydropower Station, China

Science.gov (United States)

Chen, Bing-Rui; Li, Qing-Peng; Feng, Xia-Ting; Xiao, Ya-Xun; Feng, Guang-Liang; Hu, Lian-Xing

2014-10-01

Severe stress release has occurred to the surrounding rocks of the typically columnar jointed basalt after excavation at the Baihetan Hydropower Station, Jinsha River, China, where cracking, collapse, and other types of failure may take place occasionally due to relaxation fracture. In order to understand the relaxation fracture characteristics of the columnar jointed basalt in the entire excavation process at the diversion tunnel of the Baihetan Hydropower Station, real-time microseismic monitoring tests were performed. First, the applicability of a geophone and accelerometer was analyzed in the columnar jointed basalt tunnel, and the results show that the accelerometer was more applicable to the cracking monitoring of the columnar jointed basalt. Next, the waveform characteristics of the microseismic signals were analyzed, and the microseismic signals were identified as follows: rock fracture signal, drilling signal, electrical signal, heavy vehicle passing signal, and blast signal. Then, the attenuation characteristics of the microseismic signals in the columnar jointed basalt tunnel were studied, as well as the types and characteristics of the columnar jointed basalt fracture. Finally, location analysis was conducted on the strong rock fracture events, in which four or more sensors were triggered, to obtain the temporal and spatial evolution characteristics and laws of the columnar jointed basalt relaxation fracture after excavation. The test results are not only of important reference value to the excavation and support of diversion tunnel at the Baihetan Hydropower Station, but also of great referential significance and value to the conduction of similar tests.

[Establishment of model of traditional Chinese medicine injections post-marketing safety monitoring].

Science.gov (United States)

Guo, Xin-E; Zhao, Yu-Bin; Xie, Yan-Ming; Zhao, Li-Cai; Li, Yan-Feng; Hao, Zhe

2013-09-01

To establish a nurse based post-marketing safety surveillance model for traditional Chinese medicine injections (TCMIs). A TCMIs safety monitoring team and a research hospital team engaged in the research, monitoring processes, and quality control processes were established, in order to achieve comprehensive, timely, accurate and real-time access to research data, to eliminate errors in data collection. A triage system involving a study nurse, as the first point of contact, clinicians and clinical pharmacists was set up in a TCM hospital. Following the specified workflow involving labeling of TCM injections and using improved monitoring forms it was found that there were no missing reports at the ratio of error was zero. A research nurse as the first and main point of contact in post-marketing safety monitoring of TCM as part of a triage model, ensures that research data collected has the characteristics of authenticity, accuracy, timeliness, integrity, and eliminate errors during the process of data collection. Hospital based monitoring is a robust and operable process.

76 FR 40735 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

Science.gov (United States)

2011-07-11

...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... East, Adelphi, MD. The conference center telephone number is: 301 985-7300. Contact Person: Kalyani...

75 FR 10490 - Joint Meeting of the Arthritis Drugs Advisory Committee and the Drug Safety and Risk Management...

Science.gov (United States)

2010-03-08

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Joint Meeting of the Arthritis Drugs Advisory Committee and the Drug Safety and Risk Management Advisory... Drug Safety and Risk Management Advisory Committee. General Function of the Committees: To provide...

Molecular monitoring of equine joint homeostasis

NARCIS (Netherlands)

de Grauw, J.C.

2010-01-01

Chronic joint disorders are a major cause of impaired mobility and loss of quality of life in both humans and horses. Regardless of the primary insult, any joint disorder is characterized by an upset in normal joint homeostasis, the balance between tissue anabolism and catabolism that is normally

78 FR 2677 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

Science.gov (United States)

2013-01-14

...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... before February 7, 2013. Time allotted for each presentation may be limited. If the number of registrants...

76 FR 59143 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

Science.gov (United States)

2011-09-23

...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the..., Adelphi, MD. The conference center telephone number is 301-985-7300. Contact Person: Kalyani Bhatt, Center...

78 FR 16271 - Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and...

Science.gov (United States)

2013-03-14

...] Joint Meeting of the Advisory Committee for Reproductive Health Drugs and the Drug Safety and Risk... Reproductive Health Drugs and the Drug Safety and Risk Management Advisory Committee. General Function of the... presentation may be limited. If the number of registrants requesting to speak is greater than can be reasonably...

Electrical Properties of PPy-Coated Conductive Fabrics for Human Joint Motion Monitoring

Directory of Open Access Journals (Sweden)

Jiyong Hu

2016-03-01

Full Text Available Body motion signals indicate several pathological features of the human body, and a wearable human motion monitoring system can respond to human joint motion signal in real time, thereby enabling the prevention and treatment of some diseases. Because conductive fabrics can be well integrated with the garment, they are ideal as a sensing element of wearable human motion monitoring systems. This study prepared polypyrrole conductive fabric by in situ polymerization, and the anisotropic property of the conductive fabric resistance, resistance–strain relationship, and the relationship between resistance and the human knee and elbow movements are discussed preliminarily.

Proceedings of second JAERI-JNC joint conference on nuclear safety research

International Nuclear Information System (INIS)

Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

2004-08-01

The second JAERI-JNC Joint Conference on Nuclear Safety Research was held on February 6, 2004 in Tokyo for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety in the New Organization. A total of 259 people participated in the conference mainly from the nuclear industries and regulatory organizations and the number was much larger than that in the last conference of 188. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Higashi, the Nuclear Safety Commissioner, made a special lecture on the radiation protection from the high-level radioactive waste disposal. Finally, a panel discussion was conducted with the title of ''how to conduct efficiently the nuclear safety research in the New Organization'' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from the regulatory organizations, nuclear industry, JAERI and JNC discussed the subject together with the participants on the floor. The panelists not from JAERI and JNC expressed their views and opinions on how to conduct efficiently the nuclear safety research in the New Organization that were valuable inputs for developing

Design of Safety Parameter Monitoring Function in a Research Reactor Facility

Energy Technology Data Exchange (ETDEWEB)

Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

Design of Safety Parameter Monitoring Function in a Research Reactor Facility

International Nuclear Information System (INIS)

Park, Jaekwan; Suh, Yongsuk

2014-01-01

The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

Development of Operational Safety Monitoring System and Emergency Preparedness Advisory System for CANDU Reactors (I)

International Nuclear Information System (INIS)

Kim, Ma Woong; Shin, Hyeong Ki; Lee, Sang Kyu; Kim, Hyun Koon; Yoo, Kun Joong; Ryu, Yong Ho; Son, Han Seong; Song, Deok Yong

2007-01-01

As increase of operating nuclear power plants, an accident monitoring system is essential to ensure the operational safety of nuclear power plant. Thus, KINS has developed the Computerized Advisory System for a Radiological Emergency (CARE) system to monitor the operating status of nuclear power plant continuously. However, during the accidents or/and incidents some parameters could not be provided from the process computer of nuclear power plant to the CARE system due to limitation of To enhance the CARE system more effective for CANDU reactors, there is a need to provide complement the feature of the CARE in such a way to providing the operating parameters using to using safety analysis tool such as CANDU Integrated Safety Analysis System (CISAS) for CANDU reactors. In this study, to enhance the safety monitoring measurement two computerized systems such as a CANDU Operational Safety Monitoring System (COSMOS) and prototype of CANDU Emergency Preparedness Advisory System (CEPAS) are developed. This study introduces the two integrated safety monitoring system using the R and D products of the national mid- and long-term R and D such as CISAS and ISSAC code

Perceptions and misconceptions regarding the Joint Commission's view of quality monitoring.

Science.gov (United States)

Patterson, C H

1989-10-01

The Joint Commission recently has revised its hospital standards for infection control to reflect more accurately current state-of-the-art practices. In addition, the Joint Commission's Agenda for Change initiatives include the development of clinical indicators; one of the topics that will be included in those clinical indicator sets will be infection control. How the hospital chooses to organize itself to conduct the historically required monitoring and evaluation of clinical patient care currently required by the standards of the Joint Commission is at the option of the hospital. How the hospital will organize and collect data specific to infection control indicators yet to be developed by the Joint Commission has not been determined and will not be defined until specific research and development projects are completed. The hospital is expected to have in place infection prevention, surveillance, and control programs; it also is expected to have in place a quality assurance program that focuses not only on solving identified problems but also on the improvement of patient care quality. How the hospitals organize and/or integrate these activities is also at its option. It is expected that qualified professionals will direct and enforce infection prevention, surveillance, and control practices; indicators for infection control can provide data that will help assess the relative success of those practices and activities. The Joint Commission is not developing the capability to judge, on its own part, the actual quality of care provided by an organization seeking accreditation. Rather, the Joint Commission is committed to developing more accurate means to evaluate the structures, processes, and outcomes of diagnosis and treatment activities, as well as their interrelationships. Clinical excellence is supported by quality in the organizational environment and the managerial and leadership contexts within which patient care is delivered. Both clinical and

Molecular monitoring of equine joint homeostasis

OpenAIRE

de Grauw, J.C.

2010-01-01

Chronic joint disorders are a major cause of impaired mobility and loss of quality of life in both humans and horses. Regardless of the primary insult, any joint disorder is characterized by an upset in normal joint homeostasis, the balance between tissue anabolism and catabolism that is normally maintained by resident articular cells. This upset is often fuelled by a local inflammatory response in the synovial membrane and the articular cartilage. Our current understanding of the pathogenesi...

[Necessity of applying pharmacovigilance in post-marketing safety monitoring of traditional Chinese medicine injections].

Science.gov (United States)

Wang, Hai-Nan; Chen, Wen; Fu, Zheng; Du, Wen-min; He, Jia

2008-03-01

Traditional Chinese medicine (TCM) injection has become one of the hotspots in the new TCM research and development. The serious adverse drug reactions happened in clinical have arosed attention widely in the whole society. It's very urgent to monitor the post-marketing safety of TCM injections. This paper elucidated the pharmacovigilance's necessity in the post-marketing safety monitoring of TCM injections, basing on the reason of safety problem of TCM injections and the future developing trend of adverse drug reaction monitoring. Also, this paper introduced the rapid signal detection method of spontaneous reporting system database by data mining technology.

High-cycle fatigue properties of small-bore socket-welded pipe joint

International Nuclear Information System (INIS)

Maekawa, Akira; Noda, Michiyasu; Suzuki, Michiaki

2009-01-01

Piping and equipment in nuclear power plants are structures including many welded joints. Reliability of welded joints is one of high-priority issues to improve the safety of nuclear power plants. However, occurrence of fatigue failures in small-bore socket-welded pipe joints by high-cycle vibrations is still reported. In this study, fatigue experiments on a socket-welded joint of austenitic stainless steel pipe was conducted under excitation conditions similar to those in actual plants to investigate vibration characteristics and fatigue strength. It was found that the natural frequency of pipe with socket-welded joint gradually decreased as fatigue damage developed, according to the Miner rule for fatigue life evaluation. The results indicate that the fatigue life of the welded pipe joint could be estimated by monitoring the decreasing ratio of the natural frequency of the pipe. The evaluation of decreasing ratio of the natural frequency in addition to fatigue damage evaluation by the Miner rule could enhance the accuracy of fatigue life evaluation. (author)

Safety measurement and monitoring in healthcare: a framework to guide clinical teams and healthcare organisations in maintaining safety

Science.gov (United States)

Vincent, Charles; Burnett, Susan; Carthey, Jane

2014-01-01

Patients, clinicians and managers all want to be reassured that their healthcare organisation is safe. But there is no consensus about what we mean when we ask whether a healthcare organisation is safe or how this is achieved. In the UK, the measurement of harm, so important in the evolution of patient safety, has been neglected in favour of incident reporting. The use of softer intelligence for monitoring and anticipation of problems receives little mention in official policy. The Francis Inquiry report into patient treatment at the Mid Staffordshire NHS Foundation Trust set out 29 recommendations on measurement, more than on any other topic, and set the measurement of safety an absolute priority for healthcare organisations. The Berwick review found that most healthcare organisations at present have very little capacity to analyse, monitor or learn from safety and quality information. This paper summarises the findings of a more extensive report and proposes a framework which can guide clinical teams and healthcare organisations in the measurement and monitoring of safety and in reviewing progress against safety objectives. The framework has been used so far to promote self-reflection at both board and clinical team level, to stimulate an organisational check or analysis in the gaps of information and to promote discussion of ‘what could we do differently’. PMID:24764136

Proceedings of third JAERI-JNC joint conference on nuclear safety research

International Nuclear Information System (INIS)

Anoda, Yoshinari; Oikawa, Tetsukuni; Araya, Fumimasa; Suzuki, Tsugio

2006-03-01

The present report is the proceedings of the third JAERI-JNC joint conference on nuclear safety research held on July 29, 2005 in Tokyo before integration of JAERI and JNC to JAEA. The conference was held for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety research in the new organization. A total of 234 people participated in the conference mainly from the nuclear industries and regulatory organizations. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Suzuki, deputy chairperson of NSC, made a special lecture on recent trends in nuclear safety regulation and expectation for the new organization. Finally, a panel discussion was conducted with the title of 'how to conduct efficiently the nuclear safety research in the new organization' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from JAERI and JNC presented and discussed the subject together with the participants on the floor. Through vigorous exchange of views in the panel discussion and descriptions on the questionnaires, it was obviously expressed that expectation to the safety research of the new

Monitor for safety engineering facility

International Nuclear Information System (INIS)

Sato, Akira; Kaneda, Mitsunori.

1982-01-01

Purpose: To improve the reactor safety and decrease misoperation upon periodical inspection by instantly obtaining the judgement for the stand-by states in engineering safety facilities of a nuclear power plant. Constitution: Process inputs representing the states of valves, pumps, flowrates or the likes of the facility are gathered into an input device and inputted to a status monitor. The status of the facility inputted to the input device are judged for each of the inputs in a judging section and recognized as a present system stand-by pattern of the system (Valve) to be inspected. While on the other hand, a normal system stand-by pattern previously stored in a memory unit is read out by an instruction from an operator console and judged by comparison with the system stand-by pattern in a comparison section. The results are displayed on a display device. Upon periodical inspection, inspection procedures stored in the memory unit are displayed on the display device by the instruction from the operator console. (Seki, T.)

Neural Net Safety Monitor Design

Science.gov (United States)

Larson, Richard R.

2007-01-01

The National Aeronautics and Space Administration (NASA) at the Dryden Flight Research Center (DFRC) has been conducting flight-test research using an F-15 aircraft (figure 1). This aircraft has been specially modified to interface a neural net (NN) controller as part of a single-string Airborne Research Test System (ARTS) computer with the existing quad-redundant flight control system (FCC) shown in figure 2. The NN commands are passed to FCC channels 2 and 4 and are cross channel data linked (CCDL) to the other computers as shown. Numerous types of fault-detection monitors exist in the FCC when the NN mode is engaged; these monitors would cause an automatic disengagement of the NN in the event of a triggering fault. Unfortunately, these monitors still may not prevent a possible NN hard-over command from coming through to the control laws. Therefore, an additional and unique safety monitor was designed for a single-string source that allows authority at maximum actuator rates but protects the pilot and structural loads against excessive g-limits in the case of a NN hard-over command input. This additional monitor resides in the FCCs and is executed before the control laws are computed. This presentation describes a floating limiter (FL) concept1 that was developed and successfully test-flown for this program (figure 3). The FL computes the rate of change of the NN commands that are input to the FCC from the ARTS. A window is created with upper and lower boundaries, which is constantly floating and trying to stay centered as the NN command rates are changing. The limiter works by only allowing the window to move at a much slower rate than those of the NN commands. Anywhere within the window, however, full rates are allowed. If a rate persists in one direction, it will eventually hit the boundary and be rate-limited to the floating limiter rate. When this happens, a persistent counter begins and after a limit is reached, a NN disengage command is generated. The

Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. [National report from Norway, fourth review meeting, 14-23 May 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-15

This report contains the national report from Norway to the fourth review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14 to 23 May 2012. (Author)

Indicators to monitor NPP operational safety performance

International Nuclear Information System (INIS)

Gomez-Cobo, Ana

2002-01-01

Since December 1995 the IAEA activities on safety performance indicators focused on the elaboration of a framework for the establishment of an operational safety performance indicator programme. The development of this framework began with the consideration of the concept of NPP operational safety performance and the identification of operational safety attributes. For each operational safety attribute, overall indicators, envisioned as providing an overall evaluation of relevant aspects of safety performance, were established. Associated with each overall indicator is a level of strategic indicators intended to provide a bridge from overall to specific indicators. Finally each strategic indicator was supported by a set of specific indicators, which represent quantifiable measures of performance. The programme development was enhanced by pilot plant studies, conducted over a 15 month period from January 1998 to March 1999. The result of all this work is compiled in the IAEA-TECDOC-1141, to be published shortly. This paper presents a summary of this IAEA TECDOC. It describes the operational safety performance indicator framework proposed and discusses the results of and lessons learned from the pilot studies. Despite the efforts described, it is clear that additional research is still necessary in areas such as plant-specific adaptation of proposed frameworks in order to suit individual data collection systems and plant characteristics, indicator selection, indicator definition, goal setting, action thresholds, analysis of trends, indicator display systems, analysis of overall safety performance (i.e., aggregation or combination of indicators), safety culture indicators, qualitative indicators, and use of additional indicators to address issues such as industrial safety attitude and performance, staff welfare, and environmental compliance. This is the rationale for a new IAEA Coordinated Research Project on 'Development and application of indicators to monitor NPP

Selection of indicators for continuous monitoring of patient safety: recommendations of the project 'safety improvement for patients in Europe'

DEFF Research Database (Denmark)

Kristensen, Solvejg; Mainz, Jan; Bartels, Paul

2009-01-01

such as culture, infections, surgical complications, medication errors, obstetrics, falls and specific diagnostic areas. CONCLUSION: The patient safety indicators recommended present a set of possible measures of patient safety. One of the future perspectives of implementing patient safety indicators...... for systematic monitoring is that it will be possible to continuously estimate the prevalence and incidence of patient safety quality problems. The lesson learnt from quality improvement is that it will pay off in terms of improving patient safety....

Monitoring work zone safety and mobility impacts in Texas.

Science.gov (United States)

2009-05-01

In this report, Texas Transportation Institute researchers identify key work zone safety and mobility : performance measures that the Texas Department of Transportation (TxDOT) should target as part of a work : zone monitoring program within a distri...

Internet of Things Based Combustible Ice Safety Monitoring System Framework

Science.gov (United States)

Sun, Enji

2017-05-01

As the development of human society, more energy is requires to meet the need of human daily lives. New energies play a significant role in solving the problems of serious environmental pollution and resources exhaustion in the present world. Combustible ice is essentially frozen natural gas, which can literally be lit on fire bringing a whole new meaning to fire and ice with less pollutant. This paper analysed the advantages and risks on the uses of combustible ice. By compare to other kinds of alternative energies, the advantages of the uses of combustible ice were concluded. The combustible ice basic physical characters and safety risks were analysed. The developments troubles and key utilizations of combustible ice were predicted in the end. A real-time safety monitoring system framework based on the internet of things (IOT) was built to be applied in the future mining, which provide a brand new way to monitoring the combustible ice mining safety.

Simultaneous sequential monitoring of efficacy and safety led to masking of effects.

Science.gov (United States)

van Eekelen, Rik; de Hoop, Esther; van der Tweel, Ingeborg

2016-08-01

Usually, sequential designs for clinical trials are applied on the primary (=efficacy) outcome. In practice, other outcomes (e.g., safety) will also be monitored and influence the decision whether to stop a trial early. Implications of simultaneous monitoring on trial decision making are yet unclear. This study examines what happens to the type I error, power, and required sample sizes when one efficacy outcome and one correlated safety outcome are monitored simultaneously using sequential designs. We conducted a simulation study in the framework of a two-arm parallel clinical trial. Interim analyses on two outcomes were performed independently and simultaneously on the same data sets using four sequential monitoring designs, including O'Brien-Fleming and Triangular Test boundaries. Simulations differed in values for correlations and true effect sizes. When an effect was present in both outcomes, competition was introduced, which decreased power (e.g., from 80% to 60%). Futility boundaries for the efficacy outcome reduced overall type I errors as well as power for the safety outcome. Monitoring two correlated outcomes, given that both are essential for early trial termination, leads to masking of true effects. Careful consideration of scenarios must be taken into account when designing sequential trials. Simulation results can help guide trial design. Copyright © 2016 Elsevier Inc. All rights reserved.

[Safety monitoring of cell-based medicinal products (CBMPs)].

Science.gov (United States)

Funk, Markus B; Frech, Marion; Spranger, Robert; Keller-Stanislawski, Brigitte

2015-11-01

Cell-based medicinal products (CBMPs), a category of advanced-therapy medicinal products (ATMPs), are authorised for the European market by the European Commission by means of the centralized marketing authorisation. By conforming to the German Medicinal Products Act (Sec. 4b AMG), national authorisation can be granted by the Paul-Ehrlich-Institut in Germany exclusively for ATMPs not based on a routine manufacturing procedure. In both procedures, quality, efficacy, and safety are evaluated and the risk-benefit balance is assessed. For the centralised procedure, mainly controlled clinical trial data must be submitted, whereas the requirements for national procedures could be modified corresponding to the stage of development of the ATMP. After marketing authorization, the marketing authorization/license holder is obligated to report all serious adverse reactions to the competent authority and to provide periodic safety update reports. If necessary, post-authorization safety studies could be imposed. On the basis of these regulatory measures, the safety of advanced therapies can be monitored and improved.

Artificial neural network for research reactor safety status monitoring

International Nuclear Information System (INIS)

Varde, P.V.

2001-01-01

During reactor upset/abnormal conditions, emphasis is placed on plant operator's ability to quickly identify the problem and perform diagnosis and initiate recovery action to ensure safety of the plant. However, the reliability of human action is adversely affected at the time of crisis, due to the time stress and psychological factors. Availability of operational aids capable of monitoring the status of the plant and quickly identifying the deviation from normal operation is expected to significantly improve the operator reliability. Artificial Neural Network (based on Back Propagation Algorithm) has been developed and applied for reactor safety status monitoring, as part of an Operator Support System. ANN has been trained for 14 different plant states using 42 input symptom patterns. Recall tests performed on the ANN show that the system was able to identify the plant state with reasonable accuracy. (author)

Indicators to monitor NPP safety performance. Working material

International Nuclear Information System (INIS)

1997-01-01

Numerical indicators to monitor safety status and overall safety performance of nuclear power plants (NPPs) are used by operators and some regulators worldwide. During the last few years, the IAEA, through Technical Committee Meetings and Consultants' Meetings has worked on this area. This report presents a framework for nuclear power plant safety performance indicators that was developed during two consultant meetings held at the IAEA headquarters in Vienna in December 1995 and November 1996. Annex 2 on risk based indicators was prepared during a consultants' meeting held in Vienna in July 1996. An additional outcome from these activities, was the recommendation that the IAEA conduce pilot exercises at several nuclear power plants that might be interested to participate, in order to test the validity of the concept and its usefulness. 6 figs

Indicators for monitoring of safety operation and condition of nuclear power stations

International Nuclear Information System (INIS)

Manova, D.

2001-01-01

A common goal of all employees in the nuclear power field is safety operation of nuclear power stations. The evaluation and control of NPP safety operation are a part of the elements of safety management. The present report is related only to a part of the total assessment and control of the plant safety operation, namely - the indicator system for monitoring of Kozloduy NPP operation and condition. (author)

A Novel Series Connected Batteries State of High Voltage Safety Monitor System for Electric Vehicle Application

Directory of Open Access Journals (Sweden)

Qiang Jiaxi

2013-01-01

Full Text Available Batteries, as the main or assistant power source of EV (Electric Vehicle, are usually connected in series with high voltage to improve the drivability and energy efficiency. Today, more and more batteries are connected in series with high voltage, if there is any fault in high voltage system (HVS, the consequence is serious and dangerous. Therefore, it is necessary to monitor the electric parameters of HVS to ensure the high voltage safety and protect personal safety. In this study, a high voltage safety monitor system is developed to solve this critical issue. Four key electric parameters including precharge, contact resistance, insulation resistance, and remaining capacity are monitored and analyzed based on the equivalent models presented in this study. The high voltage safety controller which integrates the equivalent models and control strategy is developed. By the help of hardware-in-loop system, the equivalent models integrated in the high voltage safety controller are validated, and the online electric parameters monitor strategy is analyzed and discussed. The test results indicate that the high voltage safety monitor system designed in this paper is suitable for EV application.

A novel series connected batteries state of high voltage safety monitor system for electric vehicle application.

Science.gov (United States)

Jiaxi, Qiang; Lin, Yang; Jianhui, He; Qisheng, Zhou

2013-01-01

Batteries, as the main or assistant power source of EV (Electric Vehicle), are usually connected in series with high voltage to improve the drivability and energy efficiency. Today, more and more batteries are connected in series with high voltage, if there is any fault in high voltage system (HVS), the consequence is serious and dangerous. Therefore, it is necessary to monitor the electric parameters of HVS to ensure the high voltage safety and protect personal safety. In this study, a high voltage safety monitor system is developed to solve this critical issue. Four key electric parameters including precharge, contact resistance, insulation resistance, and remaining capacity are monitored and analyzed based on the equivalent models presented in this study. The high voltage safety controller which integrates the equivalent models and control strategy is developed. By the help of hardware-in-loop system, the equivalent models integrated in the high voltage safety controller are validated, and the online electric parameters monitor strategy is analyzed and discussed. The test results indicate that the high voltage safety monitor system designed in this paper is suitable for EV application.

Understanding of safety monitoring in clinical trials by individuals with CF or their parents: A qualitative analysis.

Science.gov (United States)

Kern-Goldberger, Andrew S; Hessels, Amanda J; Saiman, Lisa; Quittell, Lynne M

2018-03-14

Recruiting both pediatric and adult participants for clinical trials in CF is currently of paramount importance as numerous new therapies are being developed. However, recruitment is challenging as parents of children with CF and adults with CF cite safety concerns as a principal barrier to enrollment. In conjunction with the CF Foundation (CFF) Data Safety Monitoring Board (DSMB), a pilot brochure was developed to inform patients and parents of the multiple levels of safety monitoring; the CFF simultaneously created an infographic representing the safety monitoring process. This study explores the attitudes and beliefs of CF patients and families regarding safety monitoring and clinical trial participation, and elicits feedback regarding the educational materials. Semi-structured interviews were conducted using a pre-tested interview guide and audio-recorded during routine CF clinic visits. Participants included 5 parents of children with CF quotations: attitudes toward clinical trials, safety values, conceptualizing the safety monitoring process, and priorities for delivery of patient education. Participant feedback was used to revise the pilot brochure; text was shortened, unfamiliar words clarified (e.g., "pipeline"), abbreviations eliminated, and redundancy avoided. Qualitative analysis of CF patient and family interviews provided insights into barriers to participation in clinical trials, safety concerns, perspectives on safety monitoring and educational priorities. We plan a multicenter study to determine if the revised brochure reduces knowledge, attitude and practice barriers regarding participation in CF clinical trials. Copyright © 2018 European Cystic Fibrosis Society. Published by Elsevier B.V. All rights reserved.

Multidisciplinary training program to create new breed of radiation monitor: the health and safety technician

International Nuclear Information System (INIS)

Vance, W.F.

1979-01-01

A multidiscipline training program established to create a new monitor, theHealth and Safety Technician, is described. The training program includes instruction in fire safety, explosives safety, industrial hygiene, industrial safety, health physics, and general safety practices

Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Report of the Federal Republic of Germany for the sixth review meeting in May 2018

International Nuclear Information System (INIS)

2017-08-01

The joint convention on the safety of spent fuel management and on the safety of radioactive waste management covers the following topics: historical development and actual status of the civil use of nuclear power, politics and the spent fuel management, inventories and listing, legislation and executive systems, other safeguard regulations, safety during spent fuel handling, safety during radioactive waste processing, transport across national borders, disused enclosed radioactive sources, general regulations for safety enhancement.

An Overview of the NASA Aviation Safety Program Propulsion Health Monitoring Element

Science.gov (United States)

Simon, Donald L.

2000-01-01

The NASA Aviation Safety Program (AvSP) has been initiated with aggressive goals to reduce the civil aviation accident rate, To meet these goals, several technology investment areas have been identified including a sub-element in propulsion health monitoring (PHM). Specific AvSP PHM objectives are to develop and validate propulsion system health monitoring technologies designed to prevent engine malfunctions from occurring in flight, and to mitigate detrimental effects in the event an in-flight malfunction does occur. A review of available propulsion system safety information was conducted to help prioritize PHM areas to focus on under the AvSP. It is noted that when a propulsion malfunction is involved in an aviation accident or incident, it is often a contributing factor rather than the sole cause for the event. Challenging aspects of the development and implementation of PHM technology such as cost, weight, robustness, and reliability are discussed. Specific technology plans are overviewed including vibration diagnostics, model-based controls and diagnostics, advanced instrumentation, and general aviation propulsion system health monitoring technology. Propulsion system health monitoring, in addition to engine design, inspection, maintenance, and pilot training and awareness, is intrinsic to enhancing aviation propulsion system safety.

Assessing the impact of safety monitoring on the efficacy analysis in large Phase III group sequential trials with non-trivial safety event rate.

Science.gov (United States)

Weng, Yanqiu; Palesch, Yuko Y; DeSantis, Stacia M; Zhao, Wenle

2016-01-01

In Phase III clinical trials for life-threatening conditions, some serious but expected adverse events, such as early deaths or congestive heart failure, are often treated as the secondary or co-primary endpoint, and are closely monitored by the Data and Safety Monitoring Committee (DSMC). A naïve group sequential design (GSD) for such a study is to specify univariate statistical boundaries for the efficacy and safety endpoints separately, and then implement the two boundaries during the study, even though the two endpoints are typically correlated. One problem with this naïve design, which has been noted in the statistical literature, is the potential loss of power. In this article, we develop an analytical tool to evaluate this negative impact for trials with non-trivial safety event rates, particularly when the safety monitoring is informal. Using a bivariate binary power function for the GSD with a random-effect component to account for subjective decision-making in safety monitoring, we demonstrate how, under common conditions, the power loss in the naïve design can be substantial. This tool may be helpful to entities such as the DSMCs when they wish to deviate from the prespecified stopping boundaries based on safety measures.

Determination of Parachute Joint Factors using Seam and Joint Testing

Science.gov (United States)

Mollmann, Catherine

2015-01-01

This paper details the methodology for determining the joint factor for all parachute components. This method has been successfully implemented on the Capsule Parachute Assembly System (CPAS) for the NASA Orion crew module for use in determining the margin of safety for each component under peak loads. Also discussed are concepts behind the joint factor and what drives the loss of material strength at joints. The joint factor is defined as a "loss in joint strength...relative to the basic material strength" that occurs when "textiles are connected to each other or to metals." During the CPAS engineering development phase, a conservative joint factor of 0.80 was assumed for each parachute component. In order to refine this factor and eliminate excess conservatism, a seam and joint testing program was implemented as part of the structural validation. This method split each of the parachute structural joints into discrete tensile tests designed to duplicate the loading of each joint. Breaking strength data collected from destructive pull testing was then used to calculate the joint factor in the form of an efficiency. Joint efficiency is the percentage of the base material strength that remains after degradation due to sewing or interaction with other components; it is used interchangeably with joint factor in this paper. Parachute materials vary in type-mainly cord, tape, webbing, and cloth -which require different test fixtures and joint sample construction methods. This paper defines guidelines for designing and testing samples based on materials and test goals. Using the test methodology and analysis approach detailed in this paper, the minimum joint factor for each parachute component can be formulated. The joint factors can then be used to calculate the design factor and margin of safety for that component, a critical part of the design verification process.

Noninvasive Hemoglobin Monitoring: A Rapid, Reliable, and Cost-Effective Method Following Total Joint Replacement.

Science.gov (United States)

Martin, J Ryan; Camp, Christopher L; Stitz, Amber; Young, Ernest Y; Abdel, Matthew P; Taunton, Michael J; Trousdale, Robert T

2016-03-02

Noninvasive hemoglobin (nHgb) monitoring was initially introduced in the intensive care setting as a means of rapidly assessing Hgb values without performing a blood draw. We conducted a prospective analysis to compare reliability, cost, and patient preference between nHgb monitoring and invasive Hgb (iHgb) monitoring performed via a traditional blood draw. We enrolled 100 consecutive patients undergoing primary or revision total hip or total knee arthroplasty. On postoperative day 1, nHgb and iHgb values were obtained within thirty minutes of one another. iHgb and nHgb values, cost, patient satisfaction, and the duration of time required to obtain each reading were recorded. The concordance correlation coefficient (CCC) was utilized to evaluate the agreement of the two Hgb measurement methods. Paired t tests and Wilcoxon signed-rank tests were utilized to compare mean Hgb values, time, and pain for all readings. The mean Hgb values did not differ significantly between the two measurement methods: the mean iHgb value (and standard deviation) was 11.3 ± 1.4 g/dL (range, 8.2 to 14.3 g/dL), and the mean nHgb value was 11.5 ± 1.8 g/dL (range, 7.0 to 16.0 g/dL) (p = 0.11). The CCC between the two Hgb methods was 0.69. One hundred percent of the patients with an nHgb value of ≥ 10.5 g/dL had an iHgb value of >8.0 g/dL. The mean time to obtain an Hgb value was 0.9 minute for the nHgb method and 51.1 minutes for the iHgb method (p measurement, resulting in a savings of $26 per Hgb assessment when the noninvasive method is used. Noninvasive Hgb monitoring was found to be more efficient, less expensive, and preferred by patients compared with iHgb monitoring. Providers could consider screening total joint arthroplasty patients with nHgb monitoring and only order iHgb measurement if the nHgb value is protocol had been applied to the first blood draw in our 100 patients, approximately $2000 would have been saved. Extrapolated to the U.S. total joint arthroplasty practice

Development of radiation safety monitoring system at gamma greenhouse gamma facility

International Nuclear Information System (INIS)

Hairul Nizam Idris; Azimawati Ahmad, Ahmad Zaki Hussain; Ahmad Fairuz Mohd Nasir

2009-01-01

This paper is discussing about installation of radiation safety monitoring system at Gamma Greenhouse Gamma facility, Agrotechnology and Bioscience Division (BAB). This facility actually is an outdoor type irradiation facility, which first in Nuclear Malaysia and the only one in Malaysia. Source Cs-137 (801 Curie) was use as radiation source and it located at the centre of 30 metres diameter size of open irradiation area. The radiation measurement and monitoring system to be equipped in this facility were required the proper equipment and devices, specially purpose for application at outside of building. Research review, literature study and discussion with the equipment manufacturers was being carried out, in effort to identify the best system should be developed. Factors such as tropical climate, environment surrounding and security were considered during selecting the proper system. Since this facility involving with panoramic radiation type, several critical and strategic locations have been fixed with radiation detectors, up to the distance at 200 meter from the radiation source. Apart from that, this developed system also was built for capable to provide the online real-time reading (using internet). In general, it can be summarized that the radiation safety monitoring system for outdoor type irradiation facility was found much different and complex compared to the system for indoor type facility. Keyword: radiation monitoring, radiation safety, Gamma Greenhouse, outdoor irradiation facility, panoramic radiation. (Author)

BARC-risk monitor- a tool for operational safety assessment in nuclear power plants

International Nuclear Information System (INIS)

Vinod, Gopika; Saraf, R.K.; Babar, A.K.; Hadap, Nikhil

2000-12-01

Probabilistic safety assessment has become a key tool as on today to identify and understand nuclear power plant vulnerabilities. As a result of the availability of these PSA studies, there is a desire to use them to enhance plant safety and to operate the nuclear stations in the most efficient manner. Risk monitor is a PC based tool, which computes the real time safety level and assists plant personnel to manage day-to-day activities. Risk monitor is a PC based user friendly software tool used for modification and re-analysis of a nuclear power plant. Operation of risk monitor is based on PSA methods for assisting in day to day applications. Risk monitoring programs can assess the risk profile and are used to optimise the operation of nuclear power plants with respect to a minimum risk level over the operating time. This report presents the background activities of risk monitor, its application areas and also gives the status of such tools in international scenarios. The software is based on the PSA model of Kaiga generating station and would be applicable to similar design configuration. (author)

Reactivity monitoring for safety purposes on the UK prototype fast reactor

International Nuclear Information System (INIS)

Lord, D.J.; Wilkes, D.J.

1987-01-01

The small size and high rating of the liquid metal cooled fast breeder reactor (LMFBR) make the provision of safety related instrumentation for individual subassemblies both difficult and expensive. Global monitoring of the core is thus very attractive. Reactivity monitoring is an important part of such global monitoring. Reactivity monitoring on a short timescale (a few seconds) is used on the UK Prototype Fast Reactor (PFR) as a trip parameter and long-term reactivity monitoring is being developed as a means of providing early warning of slowly developing faults. Results are presented from PFR to demonstrate the capabilities of reactivity monitoring in an operational fast reactor power station. (author)

75 FR 36427 - Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management...

Science.gov (United States)

2010-06-25

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001] Joint Meeting of the Arthritis Advisory Committee and the Drug Safety and Risk Management Advisory Committee; Notice of Meeting AGENCY: Food and Drug Administration, HHS. ACTION: Notice. This notice...

The Security Plan for the Joint Euratom/IAEA Remote Monitoring Network

International Nuclear Information System (INIS)

Stronkhorst, J.; Schoop, K.; Ruuska, K.; Kurek, S.; Levert, J.F.

2015-01-01

The European Commission and the IAEA have installed surveillance systems in all larger civil European nuclear facilities. The monitoring data is gathered by optical surveillance systems, electronic sealing systems and numerous measuring devices. The on-site joint Euratom/IAEA monitoring networks operate in general completely isolated from the operator's IT systems. To largely improve data security and reliability, remote data transmission (RDT) is installed on a growing number of sites, and the inspection data is daily transferred to the Data Collect Servers in Luxembourg and Vienna. A growing number of RDT connections and a growing number of security threats require an IT security policy that is pro-active as well as reactive in an efficient way. The risk based approach used in setting up the security plans assesses all elements of the monitoring network, from the implemented technical solution and the assessment of the security needs and threats, up to the incident handling and lessons learned. The results of the assessments are, for each individual RDT connection, described in the technical paragraphs and annexes, including system descriptions, network plans and contact information. The principles of secure data handling as implemented in the shared Euratom /IAEA monitoring network can apply to a broad range of industrial monitoring systems, where human interaction is in general the largest security risk. (author)

Proceedings of JAERI-JNC joint conference on nuclear safety research. March 7, 2003, Tokyo

International Nuclear Information System (INIS)

Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

2003-08-01

The JAERI-JNC Joint Conference on Nuclear Safety Research was held on March 7, 2003 in Tokyo with 188 participants, ahead of planned unification of JAERI and JNC in 2005. The objectives of the conference are to present recent results of safety research conducted in both institutes in accordance with the Five-Year Safety Research Plan by the Nuclear Safety Commission (NSC), and to reflect suggestions from the participants for future research program. Prof. Matsubara, Vice Chairperson of NSC, first presented a special lecture entitled 'Expectation on Future Nuclear Safety Research in Japan'. Twelve papers were then presented on the overview of research results and those of individual research activities in the fields of nuclear facilities, radioactive waste and environmental radioactivity. In the final session, a panel discussion was conducted with a title of 'Expectation on Future Nuclear Safety Research' chaired by Prof. Kimura, Chairperson of Special Committee on Nuclear Safety Research under NSC. Through the presentations and discussions, consensus has almost been obtained among participants for several key issues on safety research to be conducted by a unified new organization, such as giving priority to safety research as one of major missions, assurance of independence of safety research with the governmental funds, assurance of transparency of the planning process of safety research, separation and harmonization between safety research and developmental research, importance of maintaining fundamental research and research facilities, promotion of cooperation with relevant organizations considering the needs from industries, and importance of dissemination of research results and personnel training. The present report compiles the summaries of special lecture, papers, questions and comments, panel discussions, and OHPs presented in the conference. (author)

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

Directory of Open Access Journals (Sweden)

Mpimbaza Arthur

2008-06-01

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

Safety regulations regarding to accident monitoring and accident sampling at Russian NPPs with VVER type reactors

International Nuclear Information System (INIS)

Sharafutdinov, Rachet; Lankin, Michail; Kharitonova, Nataliya

2014-01-01

The paper describes a tendency by development of regulatory document requirements related to accident monitoring and accident sampling at Russia's NPPs. Lessons learned from the Fukushima Daiichi accident pointed at the importance and necessary to carry out an additional safety check at Russia's nuclear power plants in the preparedness for management of severe accidents at NPPs. Planned measures for improvement of severe accidents management include development and implementation of the accident instrumentation systems, providing, monitoring, management and storage of information in a severe accident conditions. The draft of Safety Guidelines <monitoring system of nuclear power plants with VVER reactors' prepared by Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) established the main criteria for accident monitoring instrumentation that can monitor relevant plant parameters in the reactor and inside containment during and after a severe accident in nuclear power plants. Development of these safety guidelines is in line with the recommendations of IAEA Action Plan on Nuclear Safety in response to the Fukushima Daiichi event and recommendations of the IAEA Nuclear Energy series Report <Monitoring Systems for Nuclear Power Plants' (Draft V 2.7). The paper presents the principles, which are used as the basis for selection of plant parameters for accident monitoring and for establishing of accident monitoring instrumentation. The recommendations to the accident sampling system capable to obtain the representative reactor coolant and containment air and fluid samples that support accurate analytical results for the parameters of interest are considered. The radiological and chemistry parameters to be monitored for primary coolant and sump and for containment air are specified. (author)

Concept for creating program-technical complex of safety monitoring with system of safety parameters presentation functions on the basis of routine WWER-1000 systems

International Nuclear Information System (INIS)

Dunaev, V.G.; Tarasov, M. V.; Povarov, P.V.

2005-01-01

Prerequisites of creating the software-hardware complex for reactor safety monitoring on the Volgodonsk NPP are analyzed and generalized. The concept of this complex is based on functions of the safety parameters presentation system. It will serve as an interface between operator and technological process and give to operator a possibility to estimate quickly the state of the safety of the nuclear power unit. The complex will be created on the basis of routine reactor monitoring and control systems intended for the WWER-1000 reactor. In addition to existing soft- and hard-wares for reactor monitoring and for analysis of technological archive, it is proposed to create and connect in parallel the new software-hardware complex which ensures calculation and presentation of generalized factors of reactor safety [ru

Monitoring consumer confidence in food safety: an exploratory study

NARCIS (Netherlands)

Jonge, de J.; Frewer, L.J.; Trijp, van J.C.M.; Renes, R.J.; Wit, de W.; Timmers, J.C.M.

2004-01-01

Abstract: In response to the potential for negative economic and societal effects resulting from a low level of consumer confidence in food safety, it is important to know how confidence is potentially influenced by external events. The aim of this article is to describe the development of a monitor

Uncertain added value of Global Trigger Tool for monitoring of patient safety in cancer care

DEFF Research Database (Denmark)

Lipczak, Henriette; Neckelmann, Kirsten; Steding-Jessen, Marianne

2011-01-01

Monitoring patient safety is a challenging task. The lack of a golden standard has contributed to the recommendation and introduction of several methods. In 2000 the Danish Lung Cancer Registry (DLCR) was established to monitor the clinical management of lung cancer. In 2008 the Global Trigger Tool...... (GTT) was recommended in Denmark as a tool for the monitoring of patient safety. Ideally, the recommendation of a new tool should be preceded by a critical assessment of its added value....

Design of safety monitor system for operation sintering furnace ME-06

International Nuclear Information System (INIS)

Sugeng Rianto; Triarjo; Djoko Kisworo; Agus Sartono

2013-01-01

Design of safety monitoring system for safety operation of sinter furnace ME-06 has been done. Parameters monitored during this operation include: temperature, gas pressure, flow rate of gas, voltage and current furnace. For sintering furnace temperature system that monitored were the temperature of the furnace temperature, the temperature of the cooling water system inlet and outlet, temperature of flow hydrogen gas inlet and outlet. For pressure system and flow rate gas sinter furnace which monitored the pressure and flow rate of hydrogen gas inlet and outlet. The system also monitors current and voltage applied to the sinter furnace heating system. Monitor system hardware consists of: the system temperature sensor, pressure, rate and data acquisition systems. While software systems using the labview driver interface that connects the hard and software systems. Function test results during sintering operation for setting the temperature 1700 °C sintering temperature increases the ramp function by 250 °C/hour average measurements obtained when the sintering time 1707.016 °C with a standard deviation of 0.38 °C. The maximum temperature of the hydrogen gas temperature 35.4 °C. The maximum temperature of the cooling water system 27.4 °C. The maximum pressure of 1,911 bar Gas Inlet and outlet of 0,051 bar. Maximum inlet gas flow 12.996 L / min and outlet 14.086 L / min. (author)

Pharmacist medication reviews to improve safety monitoring in primary care patients.

Science.gov (United States)

Gallimore, Casey E; Sokhal, Dimmy; Zeidler Schreiter, Elizabeth; Margolis, Amanda R

2016-06-01

Patients prescribed psychotropic medications within primary care are at risk of suboptimal monitoring. It is unknown whether pharmacists can improve medication safety through targeted monitoring of at risk populations. Access Community Health Centers implemented a quality improvement pilot project that included pharmacists on an integrated care team to provide medication reviews for patients. Aims were to determine whether inclusion of a pharmacist performing medication reviews within a primary care behavioral health (PCBH) practice is feasible and facilitates safe medication use. Pharmacists performed medication reviews of the electronic health record for patients referred for psychiatry consultation. Reviews were performed 1-3 months following consultation and focused on medications with known suboptimal monitoring rates. Reviews were documented within the EHR and routed to the primary care provider. Primary outcome measures were change in percentage up-to-date on monitoring and AIMS assessment, and at risk of experiencing drug interaction(s) between baseline and 3 months postreview. Secondary outcome was provider opinion of medication reviews collected via electronic survey. Reviews were performed for 144 patients. Three months postreview, percentage up-to-date on recommended monitoring increased 18% (p = .0001), at risk for drug interaction decreased 20% (p improved safety monitoring of psychotropic medications. Results identify key areas for improvement that other clinics considering integration of similar pharmacy services should consider. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

Working Group 7.1 on environmental transport, US-USSR Joint Coordinating Committee on Civilian Nuclear Reactor Safety

International Nuclear Information System (INIS)

Anspaugh, L.R.; Hendrickson, S.M.

1991-01-01

This report contains brief summaries of the status of projects of the Environmental Transport Group of the US-USSR Joint Coordinating Committee of Civilian Nuclear Reactor Safety. Projects reported on include: Management and Administration; Atmospheric Transport; Resuspension; External Dose; Terrestrial Food Chains; Aquatic Food Chains; Hydrological Transport; and Intercalibration

National report of the Slovak Republic - proposal. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Jun 2008

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Kobzova, D.; Petrik, T.; Sovcik, J.; Hekel, P.; Suess, J.; Tomek, J.; Lukacovic, J.; Hekel, P.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Konecny, L.; Parimucha, F.; Vaclav, J.; Horvath, J.; Soos, F.; Betak, A.; Pospisil, P.; Mihaly, B.; Kubala, M.; Schmidtova, B.; Orihel, M.; Vasina, D.; Balaz, J.; Ehn, L.; Micovicova, D.; Vrtoch, M.; Mlcuch, L.; Granak, P.; Meleg, J.; Sedliak, D.; Bardy, M.; Gogoliak, J.; Prazska, M.; Burslova, J.

2008-06-01

A brief national safety report of the Slovak Republic compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management in 2008 is presented. This safety report consists of following chapters: (A) Introduction; (B) Spent nuclear fuel (SNF) and radioactive waste (RAW) management conception; (C) Scope of application; (D) Spent nuclear fuel (SNF) and radioactive waste (RAW) management; (E) Legislation and regulatory framework; (F) General safety provisions; (G) Safety of spent nuclear fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Discussed sealed radioactive sources; (K) Planned measures to improve safety; (L) Annexes

Guidance on the implementation of a risk based safety performance monitoring system for nuclear power plants

International Nuclear Information System (INIS)

Sewell, R.T.; Kuritzky, A.S.; Khatib-Rahbar, M.

1997-05-01

The principal objective of the present study is to review and evaluate existing Performance Indicator (PI) monitoring programs, and to develop and demonstrate an overall PSA-based methodology and framework for the monitoring and use of risk-based PIs and SIs (Safety Indicator), that would enable: Identification of trends and patterns in safety performance at a specific plant and a population of plants; Assessment of the significance of the trends and patterns; Identification of precursors of accident sequences and safety reductions; Identification of the most critical functional areas of concern, especially as they relate to a defense-in-depth safety philosophy; Comparison of safety performance trends at a plant with those at comparable plants; Incorporation of the PIs and SIs into a risk- and performance-based decision process. To support the overall project objective, it is important that information needs and data collection procedures are clearly outlined. Of key significance in this regard is the premise that a performance monitoring system should not be burdened by an excessive number of low-level PIs that may have only a peripheral relationship to safety. Other supporting objectives of the study include: To identify and discuss other issues pertaining to the practical implementation of a safety performance monitoring system (outlining the databases and algorithms needed); and to demonstrate implementation of the preliminary guidance for monitoring and use of the selected set of PIs and SIs, within the proposed framework, via application to the operating history of a NPP having a PSA and readily available event data

Monitoring road safety development at regional level: A case study in the ASEAN region.

Science.gov (United States)

Chen, Faan; Wang, Jianjun; Wu, Jiaorong; Chen, Xiaohong; Zegras, P Christopher

2017-09-01

Persistent monitoring of progress, evaluating the results of interventions and recalibrating to achieve continuous improvement over time is widely recognized as being crucial towards the successful development of road safety. In the ASEAN (Association of Southeast Asian Nations) region there is a lack of well-resourced teams that contain multidisciplinary safety professionals, and specialists in individual countries, who are able to carry out this work effectively. In this context, not only must the monitoring framework be effective, it must also be easy to use and adapt. This paper provides a case study that can be easily reproduced; based on an updated and refined Road Safety Development Index (RSDI), by means of the RSR (Rank-sum ratio)-based model, for monitoring/reporting road safety development at regional level. The case study was focused on the road safety achievements in eleven Southeast Asian countries; identifying the areas of poor performance, potential problems and delays. These countries are finally grouped into several classes based on an overview of their progress and achievements regarding to road safety. The results allow the policymakers to better understand their own road safety progress toward their desired impact; more importantly, these results enable necessary interventions to be made in a quick and timely manner. Keeping action plans on schedule if things are not progressing as desired. This would avoid 'reinventing the wheel' and trial and error approaches to road safety, making the implementation of action plans more effective. Copyright © 2017 Elsevier Ltd. All rights reserved.

Clinical efficacy and safety of Gubitong Recipe () in treating osteoarthritis of knee joint.

Science.gov (United States)

Tao, Qing-wen; Xu, Yuan; Jin, Di-er; Yan, Xiao-ping

2009-12-01

To observe the therapeutic efficacy and safety of Gubitong Recipe (, GBT) in treating osteoarthritis (OA) of knee joint. Ninety patients with knee osteoarthritis were equally assigned, according to a randomizing digital table, to the treatment group and the control group. The treatment group was treated with GBT Decoction one dose every day and the control group with glucosamine sulfate 500 mg thrice a day, respectively, for eight successive weeks. Besides, diclofenac sodium could be given as supplementary dugs with the dosage used recorded if necessary. Western Ontario and McMaster Universities Osteoarthritis Index (WOMAC, an index reflecting the degree of joint pain, stiffness, and dysfunction) in patients was assessed before and after treatment, and the patients' symptoms were evaluated by visual analogue scale (VAS) as well. Moreover, erythrocyte sedimentation rate (ESR), blood C-reactive protein (CRP), blood and urinary routine tests, liver and kidney function examination, and the adverse reaction that occurred during the treatment period were observed. WOMAC index and integral VAS value were lowered in both groups after treatment, showing significant statistical difference as compared with before treatment (P<0.05), but the decrement of WOMAC index in the treatment group was more significant than that in the control group (P<0.05). ESR and CRP levels remained unchanged in all patients, and the proportion and mean dosage of diclofenac sodium used were similar in the two groups. No evident adverse reaction occurred during the treatment period. GBT is an effective and safe recipe for the treatment of osteoarthritis of knee joint, which could alleviate the joint pain, stiffness, and dysfunction.

Nordic studies in reactor safety

International Nuclear Information System (INIS)

Pershagen, N.

1993-01-01

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

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

Directory of Open Access Journals (Sweden)

Byeong-Wook Nam

2015-09-01

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

Sweden's second national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2005-01-01

Article 32 of the Joint Convention calls for a self-assessment by each Contracting Party regarding compliance with the obligations of the Convention. Sweden's self-assessment has demonstrated compliance with all the obligations of the Convention, as shown in detail in sections B to K of this report. Having taken a very active part in the creation of the Joint Convention, Sweden wishes to emphasise the incentive character of the Convention. In Sweden's opinion, the Convention implies a commitment to continuous improvement of safety whenever operating experience, safety research or technical development indicates that there is room for such improvement. Continuous learning from experience and a proactive approach to safety are in fact corner stones of the current Swedish nuclear and radiation safety work, both for the industry and the regulatory bodies. Therefore, Sweden has found it important that its National Report highlights strong features in national practices, as well as areas in which improvements are justified. Implementation of such improvements should then be followed up in the National Reports to subsequent Review Meetings. The major events in the Swedish nuclear programme since the first report to the Convention was issued are: - The general safety regulations of SKI have been revised and issued as SKIFS 2004:1. - A commission of inquiry has been carried out in order to review and suggest improvements to the financing system. - The second unit of the twin nuclear power plant unit at Barsebaeck (Barsebaeck 2) was permanently shut down 31 May 2005. The first unit (Barsebaeck 1) was closed in 1999. - The research reactors R2 and R2-0 at the Studsvik site were permanently shut down 16 June 2005. - The Swedish Nuclear Fuel and Waste Management Co. (SKB) has announced its decision to take over operation of the interim storage facility for spent nuclear fuel (Clab). The operation of Clab is currently contracted out to OKG, who operates the three nuclear power

49 CFR 385.333 - What happens at the end of the 18-month safety monitoring period?

Science.gov (United States)

2010-10-01

... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.333 What happens at the end of the 18-month safety monitoring period? (a) If a safety audit has been performed within... the same basis as any other carrier. (d) If a safety audit or compliance review has not been performed...

Safety KPIs - Monitoring of safety performance

Directory of Open Access Journals (Sweden)

Andrej Lališ

2014-09-01

Full Text Available This paper aims to provide brief overview of aviation safety development focusing on modern trends represented by implementation of Safety Key Performance Indicators. Even though aviation is perceived as safe means of transport, it is still struggling with its complexity given by long-term growth and robustness which it has reached today. Thus nowadays safety issues are much more complex and harder to handle than ever before. We are more and more concerned about organizational factors and control mechanisms which have potential to further increase level of aviation safety. Within this paper we will not only introduce the concept of Key Performance Indicators in area of aviation safety as an efficient control mechanism, but also analyse available legislation and documentation. Finally we will propose complex set of indicators which could be applied to Czech Air Navigation Service Provider.

Use of the Safety Monitor in operational decision-making at a nuclear generating facility

International Nuclear Information System (INIS)

Chien, Shan H.; Hook, Thomas G.; Lee, Roger J.

1998-01-01

The utilization of Safety Monitor at a nuclear generating facility in 1994 revolutionized the way US nuclear power plants manage configuration risks. At Southern California Edison (SCE) Company's San Onofre Nuclear Generating Station, it transformed probabilistic risk assessment (PRA) from a retrospective tool for understanding past risk into a prospective tool for controlling future risk. Since that time, many other nuclear utilities have taken aggressive steps in using PRA better to understand and manage risks associated with plant operation and maintenance. These utilities have employed a variety of methods ranging from systems similar to San Onofre's Safety Monitor to systems dramatically different in both technology and philosophy. In the development and use of its Safety Monitor, SCE has been guided by two philosophical goals: (1) maximize the objectivity of PRA-informed decision-making relative to managing configuration risks, and (2) ensure that risks are managed conservatively

Radiological safety system based on real-time tritium-in-air monitoring indoors and in effluents

International Nuclear Information System (INIS)

Bidica, N.; Sofalca, N; Balteanu, O.; Srefan, I.

2006-01-01

Exposure to tritium is an important health hazard in any tritium processing facility so that implementing a real-time tritium monitoring system is necessary for its operation in safety conditions. The tritium processing facility operators need to be informed at any time about the in-air tritium concentration indoors or in the stack effluents, in order to detect immediately any leaks in tritium containments, or any releases inside the buildings or to the environment. This information is very important for adopting if necessary protection measures and correcting actions as quickly as possible. In this paper we describe an improved real-time tritium monitoring system designed for the Heavy Water Detritiation Pilot Plant of National Institute for Cryogenics and Isotopes Separation, Rm. Valcea, Romania. The design of the Radiological Safety System implemented for the ICIT Water Detritiation Pilot Plant is intended to provide the maximum safety level based on the ALARA concept. The main functions of tritium monitoring system are: - monitoring the working areas and gaseous effluents by determination of the tritium-in-air activity concentration; - local and remote data display; - assessing of environment dose equivalent rates and dose equivalents in the working environment (for personnel exposure control and work planning); - assessing the total tritium activity released to the environment through ventilation exhaust stack; - safety functions, i.e., local and remote, locking/unlocking personnel access, process shut-down in emergency conditions and start of the air cleaning systems. With all these features our tritium monitoring system is really a safety system adequate for personnel and environmental protection. (authors)

Automatic crack detection and classification method for subway tunnel safety monitoring.

Science.gov (United States)

Zhang, Wenyu; Zhang, Zhenjiang; Qi, Dapeng; Liu, Yun

2014-10-16

Cracks are an important indicator reflecting the safety status of infrastructures. This paper presents an automatic crack detection and classification methodology for subway tunnel safety monitoring. With the application of high-speed complementary metal-oxide-semiconductor (CMOS) industrial cameras, the tunnel surface can be captured and stored in digital images. In a next step, the local dark regions with potential crack defects are segmented from the original gray-scale images by utilizing morphological image processing techniques and thresholding operations. In the feature extraction process, we present a distance histogram based shape descriptor that effectively describes the spatial shape difference between cracks and other irrelevant objects. Along with other features, the classification results successfully remove over 90% misidentified objects. Also, compared with the original gray-scale images, over 90% of the crack length is preserved in the last output binary images. The proposed approach was tested on the safety monitoring for Beijing Subway Line 1. The experimental results revealed the rules of parameter settings and also proved that the proposed approach is effective and efficient for automatic crack detection and classification.

Automatic Crack Detection and Classification Method for Subway Tunnel Safety Monitoring

Directory of Open Access Journals (Sweden)

Wenyu Zhang

2014-10-01

Full Text Available Cracks are an important indicator reflecting the safety status of infrastructures. This paper presents an automatic crack detection and classification methodology for subway tunnel safety monitoring. With the application of high-speed complementary metal-oxide-semiconductor (CMOS industrial cameras, the tunnel surface can be captured and stored in digital images. In a next step, the local dark regions with potential crack defects are segmented from the original gray-scale images by utilizing morphological image processing techniques and thresholding operations. In the feature extraction process, we present a distance histogram based shape descriptor that effectively describes the spatial shape difference between cracks and other irrelevant objects. Along with other features, the classification results successfully remove over 90% misidentified objects. Also, compared with the original gray-scale images, over 90% of the crack length is preserved in the last output binary images. The proposed approach was tested on the safety monitoring for Beijing Subway Line 1. The experimental results revealed the rules of parameter settings and also proved that the proposed approach is effective and efficient for automatic crack detection and classification.

Toward an integrated system concept for monitoring and evaluation of safety culture

International Nuclear Information System (INIS)

Makino, Maomi; Sakaue, Takeharu

2004-01-01

The concept of ''nuclear safety culture'' has been advocated and has been much discussed internationally by INSAG (The International Nuclear Safety Advisory Group) under IAEA (the International Atomic Energy Agency) and other institutions since Chernobyl accident. On the safety front, Japan had maintained an excellent track record in nuclear power operations throughout the 1990s. However, there have been a series of new type of problems strongly implying degradation of safety culture, e.g., Monju accident, fire and explosion accident at an Asphalt Solidification Process Facility at Tokai, falsification of annealing data at nuclear power plants (NPP), another data falsification for transport cask of spent fuel and JCO criticality accident. Then the TEPCO (Tokyo Electric Power Company) issue was revealed in 2002. Triggered by this issue, the Nuclear and Industrial Safety Agency (NISA) has been implementing a variety of improvements, one of which was the establishment of a study group in 2003, which invited experts from other fields as well as from nuclear-related industries, to study on how to implement safety culture sufficiently and possible recommendations. Subjects such as the followings piled in the study report will indicate leading keys in case it is going to realize such efforts: ''Foundation of safety culture is a quality management'' and ''Realistic and scientific technique is necessary for the evaluation of safety culture''. In order to respond to these requests, JNES have been advancing the development toward an Integrated System Concept for Monitoring and Evaluation of Safety Culture. This paper describes the outline of the study results reported by the study group and then introduces one of subsystems, SCEST, structuring the integrated system concept for Monitoring and Evaluation of Safety Culture. (author)

Vibration monitoring of long bridges and their expansion joints and seismic devices

Directory of Open Access Journals (Sweden)

Islami Kleidi

2015-01-01

Full Text Available This paper presents a number of recently installed Structural Health Monitoring (SHM systems: a on a 2km double suspension bridge; b on a long railway viaduct that has experienced cracking; and c on a steel arch bridge in a seismically active area. Damage detection techniques have been applied based on high-frequency measurements of vibrations, pressure and strain, enabling a proper understanding of the structures’ behaviour to be gained. The diverse range of applications presented, designed in collaboration with structure owners and design engineers, includes damage detection on expansion joints of suspension bridges, crack analysis and correlation with accelerations of high-speed trains, and high-frequency performance monitoring of seismic devices. These case studies, based on both static and dynamic approaches, demonstrate the usefulness and ease of use of such systems, and the enormous gains in efficiency they offer.

Construction safety monitoring based on the project's characteristic with fuzzy logic approach

Science.gov (United States)

Winanda, Lila Ayu Ratna; Adi, Trijoko Wahyu; Anwar, Nadjadji; Wahyuni, Febriana Santi

2017-11-01

Construction workers accident is the highest number compared with other industries and falls are the main cause of fatal and serious injuries in high rise projects. Generally, construction workers accidents are caused by unsafe act and unsafe condition that can occur separately or together, thus a safety monitoring system based on influencing factors is needed to achieve zero accident in construction industry. The dynamic characteristic in construction causes high mobility for workers while doing the task, so it requires a continuously monitoring system to detect unsafe condition and to protect workers from potential hazards. In accordance with the unique nature of project, fuzzy logic approach is one of the appropriate methods for workers safety monitoring on site. In this study, the focus of discussion is based on the characteristic of construction projects in analyzing "potential hazard" and the "protection planning" to be used in accident prevention. The data have been collected from literature review, expert opinion and institution of safety and health. This data used to determine hazard identification. Then, an application model is created using Delphi programming. The process in fuzzy is divided into fuzzification, inference and defuzzification, according to the data collection. Then, the input and final output data are given back to the expert for assessment as a validation of application model. The result of the study showed that the potential hazard of construction workers accident could be analysed based on characteristic of project and protection system on site and fuzzy logic approach can be used for construction workers accident analysis. Based on case study and the feedback assessment from expert, it showed that the application model can be used as one of the safety monitoring tools.

Radiation safety assessment and development of environmental radiation monitoring technology

CERN Document Server

Choi, B H; Kim, S G

2002-01-01

The Periodic Safety Review(PSR) of the existing nuclear power plants is required every ten years according to the recently revised atomic energy acts. The PSR of Kori unit 1 and Wolsong unit 1 that have been operating more than ten years is ongoing to comply the regulations. This research project started to develop the techniques necessary for the PSR. The project developed the following four techniques at the first stage for the environmental assessment of the existing plants. 1) Establishment of the assessment technology for contamination and accumulation trends of radionuclides, 2) alarm point setting of environmental radiation monitoring system, 3) Development of Radiation Safety Evaluation Factor for Korean NPP, and 4) the evaluation of radiation monitoring system performance and set-up of alarm/warn set point. A dynamic compartment model to derive a relationship between the release rates of gas phase radionuclides and the concentrations in the environmental samples. The model was validated by comparing ...

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

Directory of Open Access Journals (Sweden)

Chongshi Gu

2013-01-01

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

Joint inversion of time-lapse VSP data for monitoring CO2 injection at the Farnsworth EOR field in Texas

Science.gov (United States)

Zhang, M.; Gao, K.; Balch, R. S.; Huang, L.

2016-12-01

During the Development Phase (Phase III) of the U.S. Southwest Regional Partnership on Carbon Sequestration (SWP), time-lapse 3D vertical seismic profiling (VSP) data were acquired to monitor CO2 injection/migration at the Farnsworth Enhanced Oil Recovery (EOR) field, in partnership with the industrial partner Chaparral Energy. The project is to inject a million tons of carbon dioxide into the target formation, the deep oil-bearing Morrow Formation in the Farnsworth Unit EOR field. Quantitative time-lapse seismic monitoring has the potential to track CO2 movement in geologic carbon storage sites. Los Alamos National Laboratory (LANL) has recently developed new full-waveform inversion methods to jointly invert time-lapse seismic data for changes in elastic and anisotropic parameters in target monitoring regions such as a CO2 reservoir. We apply our new joint inversion methods to time-lapse VSP data acquired at the Farnsworth EOR filed, and present some preliminary results showing geophysical properties changes in the reservoir.

From extended integrity monitoring to the safety evaluation of satellite-based localisation system

International Nuclear Information System (INIS)

Legrand, Cyril; Beugin, Julie; Marais, Juliette; Conrard, Blaise; El-Koursi, El-Miloudi; Berbineau, Marion

2016-01-01

Global Navigation Satellite Systems (GNSS) such as GPS, already used in aeronautics for safety-related applications, can play a major role in railway safety by allowing a train to locate itself safely. However, in order to implement this positioning solution in any embedded system, its performances must be evaluated according to railway standards. The evaluation of GNSS performances is not based on the same attributes class than RAMS evaluation. Face to these diffculties, we propose to express the integrity attribute, performance of satellite-based localisation. This attribute comes from aeronautical standards and for a hybridised GNSS with inertial system. To achieve this objective, the integrity attribute must be extended to this kind of system and algorithms initially devoted to GNSS integrity monitoring only must be adapted. Thereafter, the formalisation of this integrity attribute permits us to analyse the safety quantitatively through the probabilities of integrity risk and wrong-side failure. In this paper, after an introductory discussion about the use of localisation systems in railway safety context together with integrity issues, a particular integrity monitoring is proposed and described. The detection events of this algorithm permit us to conclude about safety level of satellite-based localisation system.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2009

International Nuclear Information System (INIS)

2009-01-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2009 are published

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

International Nuclear Information System (INIS)

2011-04-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2012

International Nuclear Information System (INIS)

2012-04-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-04-15

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2014

International Nuclear Information System (INIS)

2014-04-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2014 are published.

Joint Commission

Science.gov (United States)

... for the latest publication of The Joint Commission Journal on Quality and Patient Safety (JQPS). . How We Work Process improvement program breeds quality culture, empowers staff An article in Quality Progress, June ...

The micro-processor controlled process radiation monitoring system for reactor safety systems

International Nuclear Information System (INIS)

Mizuno, K.; Noguchi, A.; Kumagami, S.; Gotoh, Y.; Kumahara, T.; Arita, S.

1986-01-01

Digital computers are soon expected to be applied to various real-time safety and safety-related systems in nuclear power plants. Hitachi is now engaged in the development of a micro-processor controlled process radiation monitoring system, which operates on digital processing methods employed with a log ratemeter. A newly defined methodology of design and test procedures is being applied as a means of software program verification for these safety systems. Recently implemented micro-processor technology will help to achieve an advanced man-machine interface and highly reliable performance. (author)

Safety Culture and Best Practices at Japan's Fusion Research Facilities

Energy Technology Data Exchange (ETDEWEB)

Rule, Keith [PPPL

2014-05-01

The Safety Monitor Joint Working Group (JWG) is one of the magnetic fusion research collaborations between the US Department of Energy and the government of Japan. Visits by occupational safety personnel are made to participating institutions on a biennial basis. In the 2013 JWG visit of US representatives to Japan, the JWG members noted a number of good safety practices in the safety walkthroughs. These good practices and safety culture topics are discussed in this paper. The JWG hopes that these practices for worker safety can be adopted at other facilities. It is a well-known, but unquantified, safety principle that well run, safe facilities are more productive and efficient than other facilities (Rule, 2009). Worker safety, worker productivity, and high quality in facility operation all complement each other (Mottel, 1995).

Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2006

International Nuclear Information System (INIS)

2003-04-01

Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (2005). Slovakia is ready to provide additional explanations to these Answers during the 2 nd Review Meeting. In the Annexes the 541/2004 Coll. LL. Act of 9 September 2004 on Peaceful Use of Nuclear Energy (Atomic Act) and on Alternations and Amendments to Some Acts

Flammable gas tank safety program: Technical basis for gas analysis and monitoring

International Nuclear Information System (INIS)

Estey, S.D.

1998-01-01

Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms

Joint inversion of geophysical data for site characterization and restoration monitoring. 1998 annual progress report

International Nuclear Information System (INIS)

Berge, P.A.; Berryman, J.G.; Roberts, J.J.; Wildenschild, D.

1998-01-01

'The purpose of this project is to develop a computer code for joint inversion of seismic and electrical data, to improve underground imaging for site characterization and remediation monitoring. The computer code developed in this project will invert geophysical data to obtain direct estimates of porosity and saturation underground, rather than inverting for seismic velocity and electrical resistivity or other geophysical properties. This is intended to be a significant improvement in the state-of-the-art of underground imaging, since interpretation of data collected at a contaminated site would become much less subjective. Potential users include DOE scientists and engineers responsible for characterizing contaminated sites and monitoring remediation of contaminated sites. In this three-year project, the authors use a multi-phase approach consisting of theoretical and numerical code development, laboratory investigations, testing on available laboratory and borehole geophysics data sets, and a controlled field experiment, to develop practical tools for joint electrical and seismic data interpretation. This report summarizes work after about 1.7 years of a 3-year project. Progress on laboratory measurements is described first, followed by progress on developing algorithms for the inversion code to relate geophysical data to porosity and saturation.'

Radiation protection and safety of radiation sources international basic safety standards

CERN Document Server

International Atomic Energy Agency. Vienna

2014-01-01

The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2006-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

A self-diagnostic adhesive for monitoring bonded joints in aerospace structures

Science.gov (United States)

Zhuang, Yitao; Li, Yu-hung; Kopsaftopoulos, Fotis; Chang, Fu-Kuo

2016-04-01

Bondline integrity is still one of the most critical concerns in the design of aircraft structures up to date. Due to the lack of confidence on the integrity of the bondline both during fabrication and service, the industry standards and regulations still require assembling the composite using conventional fasteners. Furthermore, current state-of-the-art non-destructive evaluation (NDE) and structural health monitoring (SHM) techniques are incapable of offering mature solutions on the issue of bondline integrity monitoring. Therefore, the objective of this work is the development of an intelligent adhesive film with integrated micro-sensors for monitoring the integrity of the bondline interface. The proposed method makes use of an electromechanical-impedance (EMI) based method, which is a rapidly evolving approach within the SHM family. Furthermore, an innovative screen-printing technique to fabricate piezoelectric ceramic sensors with minimal thickness has been developed at Stanford. The approach presented in this study is based on the use of (i) micro screen-printed piezoelectric sensors integrated into adhesive leaving a minimal footprint on the material, (ii) numerical and analytical modeling of the EMI spectrum of the adhesive bondline, (iii) novel diagnostic algorithms for monitoring the bondline integrity based on advanced signal processing techniques, and (iv) the experimental assessment via prototype adhesively bonded structures in static (varying loads) and dynamic (fatigue) environments. The proposed method will provide a huge confidence on the use of bonded joints for aerospace structures and lead to a paradigm change in their design by enabling enormous weight savings while maximizing the economic and performance efficiency.

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Second national report on implementation by France of its obligations under the convention

International Nuclear Information System (INIS)

2005-09-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions which took place following adoption of the Convention on Nuclear Safety in 1994. France signed the Joint Convention on 29 September 1997, the first day on which it was opened for signature, during the General Conference of the International Atomic Energy Agency (IAEA). France approved it on 22 February 2000 and deposited the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in international action to reinforce nuclear safety and it considers the Joint Convention to be a key step in this direction. The fields it covers have for a long time been part of the French approach to nuclear safety. This report, which is the second of its kind, is published in accordance with article 32 of the Joint Convention and presents the measures taken by France to meet each of the obligations set out in the Convention. The facilities and radioactive materials which are the subject of this Convention are of widely differing types and in France are covered by different regulatory authorities, as explained in section E of this report. Above a certain radioactive content threshold, a facility is referred to as a 'basic nuclear installation' (BNI) and is placed under the authority of the Nuclear Safety Authority. This category includes in particular all facilities receiving spent fuel (reactors, reprocessing plants, storage facilities, etc.), most of the facilities whose 'main purpose is management of radioactive waste' as defined by this Convention, and a large number of facilities containing radioactive waste, even if management of the waste is not their primary objective: the total number of all types of BNIs is about 125 facilities. Below this threshold, an

Separate and joint effects of alcohol and caffeine on conflict monitoring and adaptation.

Science.gov (United States)

Bailey, Kira; Amlung, Michael T; Morris, David H; Price, Mason H; Von Gunten, Curtis; McCarthy, Denis M; Bartholow, Bruce D

2016-04-01

Caffeine is commonly believed to offset the acute effects of alcohol, but some evidence suggests that cognitive processes remain impaired when caffeine and alcohol are coadministered. No previous study has investigated the separate and joint effects of alcohol and caffeine on conflict monitoring and adaptation, processes thought to be critical for self-regulation. This was the purpose of the current study. Healthy, young adult social drinkers recruited from the community completed a flanker task after consuming one of four beverages in a 2 × 2 experimental design: Alcohol + caffeine, alcohol + placebo caffeine, placebo alcohol + caffeine, or placebo alcohol + placebo caffeine. Accuracy, response time, and the amplitude of the N2 component of the event-related potential (ERP), a neural index of conflict monitoring, were examined as a function of whether or not conflict was present (i.e., whether or not flankers were compatible with the target) on both the previous trial and the current trial. Alcohol did not abolish conflict monitoring or adaptation. Caffeine eliminated conflict adaptation in sequential trials but also enhanced neural conflict monitoring. The combined effect of alcohol and caffeine was apparent only in how previous conflict affected the neural conflict monitoring response. Together, the findings suggest that caffeine leads to exaggeration of attentional resource utilization, which could provide short-term benefits but lead to problems conserving resources for when they are most needed.

The new Basic Safety Standards Directive and its implications for environmental monitoring

International Nuclear Information System (INIS)

Janssens, Augustin; Necheva, Christina; Tanner, Vesa; Turai, István

2013-01-01

Monitoring of levels of radioactivity in the environment is enshrined in Chapter 3 of the Euratom Treaty, in particular its Articles 35 and 36. These requirements in primary law have had an important impact on the importance of monitoring in Europe but have not been worked out in much detail in secondary legislation. The consolidation and revision of the Basic Safety Standards Directive was an opportunity for doing so. The requirements in Directive 96/29/Euratom had remained rather general. Now, more specific text is introduced on the establishment of discharge authorisations for radioactive effluents, and on monitoring these discharges. Requirements on estimation of public exposures and on environmental monitoring programmes have largely been copied from the old basic safety standards (BSS), however. The main novelty of the new BSS is the introduction of exposure situations, as defined by the ICRP in Publication 103 (2007). Environmental monitoring as part of the management of an emergency exposure situation is now addressed more clearly. As for existing exposure situations, indoor exposure to radon requires extensive surveys of indoor air or soil concentrations, and precise requirements are made on the management of residues from industries processing naturally occurring radioactive materials (NORM) as well as on the monitoring of building materials. Although the BSS do not address specific monitoring issues, studies have been undertaken on effluents from hospitals and on long-term management of uranium mining areas. The proposal for the new Basic Safety Standards Directive is examined in the light of experience of the accident at Fukushima Dai-ichi Nuclear Power Plant disabled by the terrible tsunami on 11 March 2011. The arrangements for information exchange in a normal situation and in an emergency exposure situation need to be looked at from this perspective as well as from the perspective of smaller incidents such as the release of 131 I in Hungary in autumn

Expansion joints for LMFBR

Energy Technology Data Exchange (ETDEWEB)

Dzenus, M.; Hundhausen, W.; Jansing, W.

1979-10-15

This discourse recounts efforts put into the SNR-2 project; specifically the development of compensation devices. The various prototypes of these compensation devices are described and the state of development reviewed. The expansion joints were developed on the basis of specific design criteria whereby differentiation is made between expansion joints of small and large nominal diameter. Expansion joints for installation in the sodium-filled primary piping are equipped with safety bellows in addition to the actual working bellows.

Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. October 2003

International Nuclear Information System (INIS)

2003-10-01

Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (April 2003). Slovakia is ready to provide additional explanations to these Answers during the 1 st Review Meeting. In the Annexes the 254/1994 Coll. LL. Act of the National Council of the Slovak Republic of 25 August 1994 on State Fund of Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes is included

Monitoring of fatigue damage in composite lap-joints using guided waves and FBG sensors

Science.gov (United States)

Karpenko, Oleksii; Khomenko, Anton; Koricho, Ermias; Haq, Mahmoodul; Udpa, Lalita

2016-02-01

Adhesive bonding is being increasingly employed in many applications as it offers possibility of light-weighting and efficient multi-material joining along with reduction in time and cost of manufacturing. However, failure initiation and progression in critical components like joints, specifically in fatigue loading is not well understood, which necessitates reliable NDE and SHM techniques to ensure structural integrity. In this work, concurrent guided wave (GW) and fiber Bragg grating (FBG) sensor measurements were used to monitor fatigue damage in adhesively bonded composite lap-joints. In the present set-up, one FBG sensor was strategically embedded in the adhesive bond-line of a lap-joint, while two other FBGs were bonded on the surface of the adherends. Full spectral responses of FBG sensors were collected and compared at specific intervals of fatigue loading. In parallel, guided waves were actuated and sensed using PZT wafers mounted on the composite adherends. Experimental results demonstrated that time-of-flight (ToF) of the fundamental modes transmitted through the bond-line and spectral response of FBG sensors were sensitive to fatigue loading and damage. Combination of guided wave and FBG measurements provided the desired redundancy and synergy in the data to evaluate the degradation in bond-line properties. Measurements taken in the presence of continuously applied load replicated the in-situ/service conditions. The approach shows promise in understanding the behavior of bonded joints subjected to complex loading.

Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. First national report on the implementation by France of the obligations of the Convention

International Nuclear Information System (INIS)

2003-03-01

The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management is supplementing the Convention of Nuclear Safety. it was approved by France on february 22, 2000 and it entered into force on June 18,2001. Article 32 obliges each contracting Party to present at the review meetings (every three years) a report on the way in which it implements the obligations of the Convention (full text of the Convention and additional information on the web site of the IAEA, its director General being the depository of the Convention. (author)

A Fiber Bragg Grating-Based Monitoring System for Roof Safety Control in Underground Coal Mining

Directory of Open Access Journals (Sweden)

Yiming Zhao

2016-10-01

Full Text Available Monitoring of roof activity is a primary measure adopted in the prevention of roof collapse accidents and functions to optimize and support the design of roadways in underground coalmines. However, traditional monitoring measures, such as using mechanical extensometers or electronic gauges, either require arduous underground labor or cannot function properly in the harsh underground environment. Therefore, in this paper, in order to break through this technological barrier, a novel monitoring system for roof safety control in underground coal mining, using fiber Bragg grating (FBG material as a perceived element and transmission medium, has been developed. Compared with traditional monitoring equipment, the developed, novel monitoring system has the advantages of providing accurate, reliable, and continuous online monitoring of roof activities in underground coal mining. This is expected to further enable the prevention of catastrophic roof collapse accidents. The system has been successfully implemented at a deep hazardous roadway in Zhuji Coal Mine, China. Monitoring results from the study site have demonstrated the advantages of FBG-based sensors over traditional monitoring approaches. The dynamic impacts of progressive face advance on roof displacement and stress have been accurately captured by the novel roadway roof activity and safety monitoring system, which provided essential references for roadway support and design of the mine.

A Study on Drug Safety Monitoring Program in India

Science.gov (United States)

Ahmad, A.; Patel, Isha; Sanyal, Sudeepa; Balkrishnan, R.; Mohanta, G. P.

2014-01-01

Pharmacovigilance is useful in assuring the safety of medicines and protecting the consumers from their harmful effects. A number of single drugs as well as fixed dose combinations have been banned from manufacturing, marketing and distribution in India. An important issue about the availability of banned drugs over the counter in India is that sufficient adverse drug reactions data about these drugs have not been reported. The most common categories of drugs withdrawn in the last decade were nonsteroidal antiinflammatory drugs (28%), antidiabetics (14.28%), antiobesity (14.28%), antihistamines (14.28%), gastroprokinetic drugs (7.14%), breast cancer and infertility drugs (7.14%), irritable bowel syndrome and constipation drugs (7.14%) and antibiotics (7.14%). Drug withdrawals from market were made mainly due to safety issues involving cardiovascular events (57.14%) and liver damage (14.28%). Majority of drugs have been banned since 3-5 years in other countries but are still available for sale in India. The present study compares the drug safety monitoring systems in the developed countries such as the USA and UK and provides implications for developing a system that can ensure the safety and efficacy of drugs in India. Absence of a gold standard for a drug safety surveillance system, variations in culture and clinical practice across countries makes it difficult for India to completely adopt another country's practices. There should be a multidisciplinary approach towards drug safety that should be implemented throughout the entire duration spanning from drug discovery to usage by consumers. PMID:25425751

Norwegian 1990 sediment data for the North Sea Task Force (NSTF) and the Joint Monitoring Group (JMG)

Energy Technology Data Exchange (ETDEWEB)

Green, N.W.; Klungsoeyr, J.

1994-12-31

This report presents the 1990 sediment data compiled as part of the Norwegian contribution to the North Sea Task Force Monitoring Master Plan and the Joint Monitoring Programme (JMP). The JMP is ordered under the Oslo and Paris Commissions, which were established to protect the marine environment against anthropogenic contamination. The stations monitored by Norway are spread over the Kattegat, Skagerrak, North Sea south to the Dogger Bank and the Faeroe Islands. The contaminants investigated are mainly selected metals, organochlorines, polycyclic aromatic hydrocarbons, and the samples were collected by gravity cores and grab/box samplers. The raw data and the mean and standard deviations of parallel samples (if relevant) are presented. 6 refs., 2 tabs.

Monitoring system of arch bridge for safety network management

Science.gov (United States)

Joo, Bong Chul; Yoo, Young Jun; Lee, Chin Hyung; Park, Ki Tae; Hwang, Yoon Koog

2010-03-01

Korea has constructed the safety management network monitoring test systems for the civil infrastructure since 2006 which includes airport structure, irrigation structure, railroad structure, road structure, and underground structure. Bridges among the road structure include the various superstructure types which are Steel box girder bridge, suspension bridge, PSC-box-girder bridge, and arch bridge. This paper shows the process of constructing the real-time monitoring system for the arch bridge and the measured result by the system. The arch type among various superstructure types has not only the structural efficiency but the visual beauty, because the arch type superstructure makes full use of the feature of curve. The main measuring points of arch bridges composited by curved members make a difference to compare with the system of girder bridges composited by straight members. This paper also shows the method to construct the monitoring system that considers the characteristic of the arch bridge. The system now includes strain gauges and thermometers, and it will include various sensor types such as CCTV, accelerometers and so on additionally. For the long term and accuracy monitoring, the latest optical sensors and equipments are applied to the system.

Considerations on monitoring needs of advanced, passive safety light water reactors for severe accident management

International Nuclear Information System (INIS)

Bava, G.; Zambardi, F.

1992-01-01

This paper deals with problems concerning information and related instrumentation needs for Accident Management (AM), with special emphasis on Severe Accidents (SA) in the new advanced, passive safety Light Water Reactors (PLWR), presently in a development stage. The passive safety conception adopted in the plants concerned goes parallel with a deeper consideration of SA, that reflects the need of increasing the plant resistance against conditions going beyond traditional ''design basis accidents''. Further, the role of Accident Management (AM) is still emphasized as last step of the defence in depth concept, in spite of the design efforts aimed to reduce human factor importance; as a consequence, the availability of pertinent information on actual plant conditions remains a necessary premise for performing preplanned actions. This information is essential to assess the evolution of the accident scenarios, to monitor the performances of the safety systems, to evaluate the ultimate challenge to the plant safety, and to implement the emergency operating procedures and the emergency plans. Based on these general purposes, the impact of the new conception on the monitoring structure is discussed, furthermore reference is made to the accident monitoring criteria applied in current plants to evaluate the requirements for possible solutions. (orig.)

Sweden's third national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2008-01-01

Article 32 of the Joint Convention calls for a self-assessment by each Contracting Party regarding compliance with the obligations of the Convention. Sweden's self-assessment has demonstrated compliance with all the obligations of the Convention, as shown in detail in sections B to J of this report. The Swedish existing nuclear power programme is since a few years under strong development. Large amounts are being invested in the 10 remaining operating reactors to prepare for long term operation and major programmes are going on to upgrade and uprate the plants. The former regulatory authorities, the Swedish Nuclear Power Inspectorate (SKI), and the Swedish Radiation Protection Authority (SSI), was merged into a new regulatory body, the Swedish Radiation Safety Authority, July 01, 2008. The new authority has been tasked with the responsibility and tasks from SKI and SSI. These developments create new challenges for the safety work of the licensees as well as for the regulatory authority. Even though comprehensive and very active programmes for the management and disposal of spent fuel and radioactive waste have been established, many challenges remain. Over the next 5-15 years several new facilities will be sited, constructed and taken into operation, e.g. an encapsulation plant and a repository for spent fuel. These activities will require substantial efforts for both the nuclear industry and the regulatory bodies. The generally positive impression reported to earlier review meetings under the Joint Convention still stands. Therefore, Sweden would like to point out the following as strong features in its national nuclear practice: The responsibility for safety is clearly defined in the Swedish legal framework. In order not to dilute the responsibility of the licence holders, the Swedish regulations are designed to define requirements to be achieved, not the detailed means to achieve them. Within the framework given by the regulations, the licence holders have to

U.S. Perspectives on the Joint Convention

International Nuclear Information System (INIS)

Strosnider, J.; Federline, M.; Camper, L.; Abu-Eid, R.; Gnugnoli, G.; Gorn, J.; Bubar, P.; Tonkay, D.

2006-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) is an international convention, under the auspices of the International Atomic Energy Agency (IAEA). It is a companion to a suite of international conventions on nuclear safety and physical security, which serve to promote a global culture for the safe use of radioactive materials. Although the U.S. was the first nation to sign the Joint Convention on September 29, 1997, the ratification process was a challenging experience for the U.S., in the face of legislative priorities dominated by concerns for national security and threats from terrorism after September 11, 2001. Notwithstanding these prevailing circumstances, the U.S. ratified the Joint Convention in 2003, just prior to the First Review Meeting of the Contracting Parties, and participated fully therein. For the United States, participation as a Contracting Party provides many benefits. These range from working with other Parties to harmonize international approaches to achieve strong and effective nuclear safety programs on a global scale, to stimulating initiatives to improve safety systems within our own domestic programs, to learning about technical innovations by other Parties that can be useful to U.S. licensees, utilities, and industry in managing safety and its associated costs in our waste management activities. The Joint Convention process also provides opportunities to identify future areas of bilateral and multilateral technical and regulatory cooperation with other Parties, as well as an opportunity for U.S. vendors and suppliers to broaden their market to include foreign clients for safety improvement equipment and services. The Joint Convention is consistent with U.S. foreign policy considerations to support, as a priority, the strengthening of the worldwide safety culture in the use of nuclear energy. Because of its many benefits, we believe it is important to take

Overview of the IAEA Joint Convention and Implementation Status of the Obligation as the Contracting Party of the 5th Joint Convention

International Nuclear Information System (INIS)

Lee, Jeong Ken; Lee, Youn Keun; Ahn, Sang Myeon

2016-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) was adopted on 5 September 1997 by a Diplomatic Conference convened by the International Atomic Energy Agency (IAEA). The Joint Convention was opened for signature at Vienna in September 1997 and will remain open for signature until its entry into force. Korean government signed the Joint Convention in 1997 and this Convention was effective in 2002 as the Convention No. 1612. This paper will show overview of the Joint Convention and implementation status of the obligation as a Contracting Party of the 5th Joint Convention. The Joint Convention is the inter-national convention organized by the IAEA. All contracting parties shall comply with rules of the Joint Convention and conduct the obligation of this convention. Korean government successfully conducted all obligation (attending Organization Meeting and Review Meeting, submitting paper including National Report, question paper and answer paper) of the 5th Joint Convention from May 2014 to May 2015, and will prepare the obligation of the 6th Joint Convention

Real-time monitoring of laser welding of galvanized high strength steel in lap joint configuration

Science.gov (United States)

Kong, Fanrong; Ma, Junjie; Carlson, Blair; Kovacevic, Radovan

2012-10-01

Two different cases regarding the zinc coating at the lap joint faying surface are selected for studying the influence of zinc vapor on the keyhole dynamics of the weld pool and the final welding quality. One case has the zinc coating fully removed at the faying surface; while the other case retains the zinc coating on the faying surface. It is found that removal of the zinc coating at the faying surface produces a significantly better weld quality as exemplified by a lack of spatters whereas intense spatters are present when the zinc coating is present at the faying surface. Spectroscopy is used to detect the optical spectra emitted from a laser generated plasma plume during the laser welding of galvanized high strength DP980 steel in a lap-joint configuration. A correlation between the electron temperature and defects within the weld bead is identified by using the Boltzmann plot method. The laser weld pool keyhole dynamic behavior affected by a high-pressure zinc vapor generated at the faying surface of galvanized steel lap-joint is monitored in real-time by a high speed charge-coupled device (CCD) camera assisted with a green laser as an illumination source.

The roles of the seismic safety and monitoring systems in the PEC fast reactor

International Nuclear Information System (INIS)

Masoni, P.; Di Tullio, E.M.; Massa, B.; Martelli, A.; Sano, T.

1988-01-01

Two different seismic systems are foreseen in the case of PEC: the seismic safety system, that provides the automatic scram, and the seismic monitoring system. During earthquake, three triaxial seismic switches are triggered if a threshold value of the ground acceleration is exceeded. In this case, the signals from the seismic switches are processed by the safety system (with a 2/3 logic) and the shutdown system is triggered. Peak acceleration is the parameter used by the safety system to quantify the seismic event. This way, however, no information is obtained with regard to earthquake frequency content. Thus, reactor safety is guaranteed by adopting a threshold considerably lower than the Z.P.A. of the Design Basis Earthquake. Furthermore, in the case of significant earthquakes, the seismic motion is measured by about 20 triaxial accelerometers, located both in the free field and on the plant's structures. Data are digitazed and recordered by the seismic monitoring system. This system also elaborates the recordered time-histories providing floor response spectra and compares such spectra to the design values. The above-mentioned elaborations and comparisons are performed in short time for two triaxial measuring positions, thus allowing the Operator to immediately get a more complete information on the seismic event. The complete set of data recorded by the seismic monitoring system also allows the actual dynamic response of the plant to be determined and compared to the design values. On the basis of this comparison the necessary safety analysis can be carried out to verify whether the design limits of the plant were respected: in the positive case the reactor can be restarted. (author)

Jointly reconstructing ground motion and resistivity for ERT-based slope stability monitoring

Science.gov (United States)

Boyle, Alistair; Wilkinson, Paul B.; Chambers, Jonathan E.; Meldrum, Philip I.; Uhlemann, Sebastian; Adler, Andy

2018-02-01

Electrical resistivity tomography (ERT) is increasingly being used to investigate unstable slopes and monitor the hydrogeological processes within. But movement of electrodes or incorrect placement of electrodes with respect to an assumed model can introduce significant resistivity artefacts into the reconstruction. In this work, we demonstrate a joint resistivity and electrode movement reconstruction algorithm within an iterative Gauss-Newton framework. We apply this to ERT monitoring data from an active slow-moving landslide in the UK. Results show fewer resistivity artefacts and suggest that electrode movement and resistivity can be reconstructed at the same time under certain conditions. A new 2.5-D formulation for the electrode position Jacobian is developed and is shown to give accurate numerical solutions when compared to the adjoint method on 3-D models. On large finite element meshes, the calculation time of the newly developed approach was also proven to be orders of magnitude faster than the 3-D adjoint method and addressed modelling errors in the 2-D perturbation and adjoint electrode position Jacobian.

[Enlightenment of adverse reaction monitoring on safety evaluation of traditional Chinese medicines].

Science.gov (United States)

Song, Hai-bo; Du, Xiao-xi; Ren, Jing-tian; Yang, Le; Guo, Xiao-xin; Pang, Yu

2015-04-01

The adverse reaction monitoring is important in warning the risks of traditional Chinese medicines at an early stage, finding potential quality problems and ensuring the safe clinical medication. In the study, efforts were made to investigate the risk signal mining techniques in line with the characteristics of traditional Chinese medicines, particularly the complexity in component, processing, compatibility, preparation and clinical medication, find early risk signals of traditional Chinese medicines and establish a traditional Chinese medicine safety evaluation system based on adverse reaction risk signals, in order to improve the target studies on traditional Chinese medicine safety, effective and timely control risks and solve the existing frequent safety issue in traditional Chinese medicines.

Two sides of the safety coin?: How patient engagement and safety climate jointly affect error occurrence in hospital units.

Science.gov (United States)

Schiffinger, Michael; Latzke, Markus; Steyrer, Johannes

2016-01-01

Safety climate (SC) and more recently patient engagement (PE) have been identified as potential determinants of patient safety, but conceptual and empirical studies combining both are lacking. On the basis of extant theories and concepts in safety research, this study investigates the effect of PE in conjunction with SC on perceived error occurrence (pEO) in hospitals, controlling for various staff-, patient-, and hospital-related variables as well as the amount of stress and (lack of) organizational support experienced by staff. Besides the main effects of PE and SC on error occurrence, their interaction is examined, too. In 66 hospital units, 4,345 patients assessed the degree of PE, and 811 staff assessed SC and pEO. PE was measured with a new instrument, capturing its core elements according to a recent literature review: Information Provision (both active and passive) and Activation and Collaboration. SC and pEO were measured with validated German-language questionnaires. Besides standard regression and correlational analyses, partial least squares analysis was employed to model the main and interaction effects of PE and SC on pEO, also controlling for stress and (lack of) support perceived by staff, various staff and patient attributes, and potential single-source bias. Both PE and SC are associated with lower pEO, to a similar extent. The joint effect of these predictors suggests a substitution rather than mutually reinforcing interaction. Accounting for control variables and/or potential single-source bias slightly attenuates some effects without altering the results. Ignoring PE potentially amounts to forgoing a potential source of additional safety. On the other hand, despite the abovementioned substitution effect and conjectures of SC being inert, PE should not be considered as a replacement for SC.

Nuclear safety. Summary of the intermediate report of the special joint parliamentary committee on nuclear safety, present and future outlook of the nuclear industry

International Nuclear Information System (INIS)

Birraux, Claude; Bataille, Christian; Sido, Bruno

2011-09-01

Following the Fukushima events, the Parliamentary Office for Scientific and Technological Assessment (OPECST) was officially asked at the end of March 2011 - jointly by the National Assembly Bureau and by the Senate Committee on the economy, sustainable development, territorial and regional planning - to carry out a study on nuclear safety, and the present and future outlook of the nuclear industry. To carry out this study, seven members of the National Assembly economic affairs and sustainable development committees were also involved, as well as eight members of the Senate Committee on the economy, sustainable development, territorial and regional planning. The first part of this study, devoted to nuclear safety, was completed on 30 June 2011 by the publication of an intermediate report. This report assembles and summarises the information collected during six public hearings and seven trips to nuclear sites. France is one of the nuclear countries where the management of safety is both the most demanding and the most transparent. In this respect, the independence of the Safety Authority is the best guarantee of strictness in the safety field and the existence of pluralistic bodies, such as the Local Information Committees, is the best guarantee of the transparency of safety. But no country can pride itself on being totally safe from a natural disaster of an unexpected scale. The French nuclear industry must therefore ratchet up one more notch its investment in safety and strengthen the means of university research. It must imagine events of even greater intensity, cascading accidents, with interactions between neighbouring industrial sites. Investment must be made by placing safety requirements above any economic consideration and in strict compliance with the specifications of public authorities supervising safety. (authors)

Third Joint GIF–IAEA Workshop on Safety Design Criteria for Sodium-Cooled Fast Reactors, 26-27 February 2013, Vienna, Austria. Summary Report

International Nuclear Information System (INIS)

2013-01-01

The main objectives of the meeting were to: • Present and share information on the work carried out by GIF, the IAEA and the Member States on the definition of safety design criteria for SFR, including safety approach and requirements on general plant design; • Present the document prepared by the GIF-SFR Task Force on Safety Design Criteria; • Present and discuss safety design concepts of SFRs under development in Member States, with particular emphasis on design measures against Design Basis Accidents and Design Extended Conditions, as well as the associated safety evaluations and supporting R&D; • Draft a room document which should be the basis of the discussion for the Panel on Safety Design Criteria of the FR13 Conference in Paris. • Discuss the results and agree on the future actions of the 3rd Joint GIF-IAEA Workshop on Safety of Sodium-Cooled Fast Reactors

Condition Monitoring and Fault Diagnosis for an Antifalling Safety Device

Directory of Open Access Journals (Sweden)

Guangxiang Yang

2015-01-01

Full Text Available There is a constant need for the safe operation and reliability of antifalling safety device (AFSD of an elevator. This paper reports an experimental study on rotation speed and catching torque monitoring and fault diagnosis of an antifalling safety device in a construction elevator. Denoising the signal using wavelet transform is presented in this paper. Based on the denoising effects for several types of wavelets, the sym8 wavelet basis, which introduces the high order approximation and an adaptive threshold, is employed for denoising the signal. The experimental result shows a maximum data error reduction of 7.5% is obtained and SNRs (signal-to-noise ratio of rotation speed and catching torque are improved for 3.9% and 6.4%, respectively.

Geoelectrical Methods and Monitoring for Dam Safety Assessment, Republic of Korea

Science.gov (United States)

Lim, S. K.; Oldenburg, D.; Kang, S.; Song, S. H.

2016-12-01

Geoelectrical methods and monitoring to detect the seepage and internal erosion are essential for the safety assessment of earth dams. This work aims to develop improved methodologies to analyze the observed data and to monitor changes in seepage flow using direct current (DC) and self-potential (SP) methods. The seasonal variation of water level at dams causes a change in seepage and water saturation and hence alters the resistivity of the dam material. DC data are sensitive to water saturation and hence changes in saturation can be obtained by repeatedly measuring DC data. However, a more diagnostic parameter for safety assessment is fluid flow, and resistivity is only weakly coupled to that. Fortunately SP signals are directly related to fluid flow, and thus an SP survey has the potential to characterize fluid flow through the earth matrix. In Korea, the safety assessment of earth fill dams has been dealt by Korea Rural Community Corporation (KRC). Most of the dams are relatively old ( >50 years), hence assessing deterioration and corresponding seepage of those dams are crucial. In order to evaluate the engineering geological properties of the soil at earth dams in Korea, two boreholes in each dam were drilled to a bedrock depth that exceeds the height of the dam. A large set of field tests, including standard penetration tests (SPT) and in-situ permeability tests, were carried out along the boreholes. However, seepage paths in the dam is complex hence those limited measurements at a few points is not sufficient to delineate the zone of preferential seepage flow. For this, KRC developed permanent DC monitoring systems at a number of agricultural dams in Korea. The data were automatically collected every 6 hours. During the monitoring, the measurements of the water level at two boreholes were gathered at the same time. In this presentation we select an agricultural dam and delineate an anomalous leakage zone by inverting and interpreting time-lapse DC resistivity

Real-Time Safety Monitoring and Prediction for the National Airspace System

Science.gov (United States)

Roychoudhury, Indranil

2016-01-01

As new operational paradigms and additional aircraft are being introduced into the National Airspace System (NAS), maintaining safety in such a rapidly growing environment becomes more challenging. It is therefore desirable to have both an overview of the current safety of the airspace at different levels of granularity, as well an understanding of how the state of the safety will evolve into the future given the anticipated flight plans, weather forecasts, predicted health of assets in the airspace, and so on. To this end, we have developed a Real-Time Safety Monitoring (RTSM) that first, estimates the state of the NAS using the dynamic models. Then, given the state estimate and a probability distribution of future inputs to the NAS, the framework predicts the evolution of the NAS, i.e., the future state, and analyzes these future states to predict the occurrence of unsafe events. The entire probability distribution of airspace safety metrics is computed, not just point estimates, without significant assumptions regarding the distribution type and or parameters. We demonstrate our overall approach by predicting the occurrence of some unsafe events and show how these predictions evolve in time as flight operations progress.

Enabling social listening for cardiac safety monitoring: Proceedings from a drug information association-cardiac safety research consortium cosponsored think tank.

Science.gov (United States)

Seifert, Harry A; Malik, Raleigh E; Bhattacharya, Mondira; Campbell, Kevin R; Okun, Sally; Pierce, Carrie; Terkowitz, Jeffrey; Turner, J Rick; Krucoff, Mitchell W; Powell, Gregory E

2017-12-01

This white paper provides a summary of the presentations and discussions from a think tank on "Enabling Social Listening for Cardiac Safety Monitoring" trials that was cosponsored by the Drug Information Association and the Cardiac Safety Research Consortium, and held at the White Oak headquarters of the US Food and Drug Administration on June 3, 2016. The meeting's goals were to explore current methods of collecting and evaluating social listening data and to consider their applicability to cardiac safety surveillance. Social listening is defined as the act of monitoring public postings on the Internet. It has several theoretical advantages for drug and device safety. First, these include the ability to detect adverse events that are "missed" by traditional sources and the ability to detect adverse events sooner than would be allowed by traditional sources, both by affording near-real-time access to data from culturally and geographically diverse sources. Social listening can also potentially introduce a novel patient voice into the conversation about drug safety, which could uniquely augment understanding of real-world medication use obtained from more traditional methodologies. Finally, it can allow for access to information about drug misuse and diversion. To date, the latter 2 of these have been realized. Although regulators from the Food and Drug Administration and the United Kingdom's Medicines and Healthcare Products Regulatory Agency participated in the think tank along with representatives from industry, academia, and patient groups, this article should not be construed to constitute regulatory guidance. Copyright © 2017 Elsevier Inc. All rights reserved.

JANNAF 28th Propellant Development and Characterization Subcommittee and 17th Safety and Environmental Protection Subcommittee Joint Meeting. Volume 1

Science.gov (United States)

Cocchiaro, James E. (Editor); Mulder, Edwin J. (Editor); Gomez-Knight, Sylvia J. (Editor)

1999-01-01

This volume contains 37 unclassified/unlimited-distribution technical papers that were presented at the JANNAF 28th Propellant Development & Characterization Subcommittee (PDCS) and 17th Safety & Environmental Protection Subcommittee (S&EPS) Joint Meeting, held 26-30 April 1999 at the Town & Country Hotel and the Naval Submarine Base, San Diego, California. Volume II contains 29 unclassified/limited-distribution papers that were presented at the 28th PDCS and 17th S&EPS Joint Meeting. Volume III contains a classified paper that was presented at the 28th PDCS Meeting on 27 April 1999. Topics covered in PDCS sessions include: solid propellant rheology; solid propellant surveillance and aging; propellant process engineering; new solid propellant ingredients and formulation development; reduced toxicity liquid propellants; characterization of hypergolic propellants; and solid propellant chemical analysis methods. Topics covered in S&EPS sessions include: space launch range safety; liquid propellant hazards; vapor detection methods for toxic propellant vapors and other hazardous gases; toxicity of propellants, ingredients, and propellant combustion products; personal protective equipment for toxic liquid propellants; and demilitarization/treatment of energetic material wastes.

HSI for monitoring the critical safety functions status tree of a NPP

International Nuclear Information System (INIS)

Oliveira, Mauro Vitor de; Almeida, Jose Carlos Soares de; Augusto, Silas Cordeiro; Jaime, Guilherme Dutra Gonzaga

2013-01-01

Critical safety function (CSF) is the most significant design concept for prioritize operator actions based on the potential threat to the three barriers (fuel cladding, primary coolant system boundary, and containment) and allows the operator to respond to these threats prior to event diagnosis. CSF has a hierarchical information structure that organizes the system variables affecting the plant safety in terms of goal-means relations. It is important that the operator should be aware of various success paths associated with each CSF in order to respond to unanticipated system failures quickly. When an emergency occurs in NPPs, the operator should monitor CSFs periodically and identify possible success paths as necessary, and try to stabilize or safely shut down the plant using emergency operating procedure (EOP) that includes steps to check the CSFs. This implies that safety function status check may become a cognitively burdensome task that needs to be supported by proper information display. The advanced human-system interface (HSI) in nuclear power plants provides an information environment that supports the operators' burdensome cognitive tasks. This paper describes a CSFs interface design for supporting the operator's tasks to monitor and identify the associated success path for Westinghouse 3-loops NPP. (author)

Criticality safety considerations. Integral Monitored Retrievable Storage (MRS) Facility

International Nuclear Information System (INIS)

1986-09-01

This report summarizes the criticality analysis performed to address criticality safety concerns and to support facility design during the conceptual design phase of the Monitored Retrievable Storage (MRS) Facility. The report addresses the criticality safety concerns, the design features of the facility relative to criticality, and the results of the analysis of both normal operating and hypothetical off-normal conditions. Key references are provided (Appendix C) if additional information is desired by the reader. The MRS Facility design was developed and the related analysis was performed in accordance with the MRS Facility Functional Design Criteria and the Basis for Design. The detailed description and calculations are documented in the Integral MRS Facility Conceptual Design Report. In addition to the summary portion of this report, explanatary notes for various terms, calculation methodology, and design parameters are presented in Appendix A. Appendix B provides a brief glossary of technical terms

A preliminary case series evaluating the safety and immediate to short-term clinical benefits of joint mobilization in hemophilic arthritis of the lower limb.

Science.gov (United States)

Scaddan, Emma; Rowell, John; O'Leary, Shaun

2017-09-01

Arthritis resulting from recurrent intra-articular bleeding in individuals with hemophilia can be severely debilitating due to joint pain and stiffness with subsequent loss of mobility and function. Very limited studies have investigated the potential benefits of joint mobilization for this condition. This case series is a preliminary investigation of safety, as well as immediate and short-term clinical benefits, associated with gentle knee and ankle joint mobilization in people with hemophilic arthropathy. A single intervention of joint mobilization was applied to the affected knees and/or ankles of 16 individuals with severe or moderate hemophilia within a public hospital setting. Adverse events, as well as immediate (pain-free passive joint range, Timed Up and Go Test with maximum pain numerical rating scale) and short-term (Lower Extremity Functional Scale) effects of the intervention were evaluated with a repeated measures ANOVA. There were no adverse events. An immediate significant increase was observed in pain-free passive ankle joint range of motion ( p  < 0.05) following the joint mobilization intervention. The findings of this case series suggest that gentle joint mobilization techniques may be safely considered as part of a multimodal management approach for hemophilic arthropathy.

Introduction of structural health and safety monitoring warning systems for Shenzhen-Hong Kong Western Corridor Shenzhen Bay Bridge

Science.gov (United States)

Li, N.; Zhang, X. Y.; Zhou, X. T.; Leng, J.; Liang, Z.; Zheng, C.; Sun, X. F.

2008-03-01

Though the brief introduction of the completed structural health and safety monitoring warning systems for Shenzhen-Hongkong western corridor Shenzhen bay highway bridge (SZBHMS), the self-developed system frame, hardware and software scheme of this practical research project are systematically discussed in this paper. The data acquisition and transmission hardware and the basic software based on the NI (National Instruments) Company virtual instruments technology were selected in this system, which adopted GPS time service receiver technology and so on. The objectives are to establish the structural safety monitoring and status evaluation system to monitor the structural responses and working conditions in real time and to analyze the structural working statue using information obtained from the measured data. It will be also provided the scientific decision-making bases for the bridge management and maintenance. Potential technical approaches to the structural safety warning systems, status identification and evaluation method are presented. The result indicated that the performance of the system has achieved the desired objectives, ensure the longterm high reliability, real time concurrence and advanced technology of SZBHMS. The innovate achievement which is the first time to implement in domestic, provide the reference for long-span bridge structural health and safety monitoring warning systems design.

Tranexamic Acid in Total Joint Arthroplasty: Efficacy and Safety

Directory of Open Access Journals (Sweden)

Mohammad Reza Rasouli

2015-01-01

Full Text Available Despite improvements in surgical and anesthetic techniques, total joint arthroplasty (TJA is still associated with substantial blood loss and postoperative anemia (1. A considerable portion of patients with postoperative anemia require blood transfusion, which has been shown to negatively affect the outcome of TJA and predisposes patients to development of surgical site infection and periprosthetic joint infection (2,3.   Various blood conservation strategies have been developed to reduce the need for allogeneic blood transfusion in patients undergoing TJA (3. Administration of tranexamic acid (TA is one of the most effective (4. TA is a synthetic lysine derivative drug that binds to plasminogen and prevents the interaction of plasminogen and fibrin, eventually leading to dissolution of fibrin clots (5.   There is level I evidence supporting the need for allogeneic transfusion in primary total hip and total knee arthroplasties, and the efficacy of TA in particular for reducing blood loss (6,7. TA is also effective in reducing the need for blood transfusion in bilateral TJA and revision surgeries (4. Moreover, when TA is used, other blood conservation strategies are rendered unnecessary (4.   The drug can be used intravenously in a weight-based manner (10-20 mg/kg, or administered 1gm intravenously at the start of surgery and 1gm intravenously at the end of surgery, or up to 3 hours after the first dose. TA can also be applied topically to the surgical site to provide hemostasis, or it can be injected intra-articularly (1g in 50 cc saline. Although oral administration of TA (25 mg/kg, maximum 2g, two hours preoperatively has also been reported to be effective, it is not routinely used in TJA patients and intravenous and topical methods are preferred (4.   Despite the proven efficacy of the use of TA in TJA, there are still some concerns about the development of venous thromboembolism (VTE after TA is used. Since VTE following TJA is

Intelligent Packaging Systems: Sensors and Nanosensors to Monitor Food Quality and Safety

Directory of Open Access Journals (Sweden)

Guillermo Fuertes

2016-01-01

Full Text Available The application of nanotechnology in different areas of food packaging is an emerging field that will grow rapidly in the coming years. Advances in food safety have yielded promising results leading to the development of intelligent packaging (IP. By these containers, it is possible to monitor and provide information of the condition of food, packaging, or the environment. This article describes the role of the different concepts of intelligent packaging. It is possible that this new technology could reach enhancing food safety, improving pathogen detection time, and controlling the quality of food and packaging throughout the supply chain.

Assessment of pharmacovigilance approaches for monitoring the safety of antimalarial drugs in pregnancy

NARCIS (Netherlands)

Dellicour, S.O.M.C.

2014-01-01

Post-marketing surveillance of drugs used in pregnancy is challenging, especially in developing countries where resources for pharmacovigilance are rare. There is a need to establish simple but effective systems to monitor safety of drugs given during pregnancy in resource constrained countries.

Research on Safety Monitoring System of Tailings Dam Based on Internet of Things

Science.gov (United States)

Wang, Ligang; Yang, Xiaocong; He, Manchao

2018-03-01

The paper designed and implemented the safety monitoring system of tailings dam based on Internet of things, completed the hardware and software design of sensor nodes, routing nodes and coordinator node by using ZigBee wireless sensor chip CC2630 and 3G/4G data transmission module, developed the software platform integrated with geographic information system. The paper achieved real-time monitoring and data collection of tailings dam dam deformation, seepage line, water level and rainfall for all-weather, the stability of tailings dam based on the Internet of things monitoring is analyzed, and realized intelligent and scientific management of tailings dam under the guidance of the remote expert system.

Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

International Nuclear Information System (INIS)

Sturm, A.; Foerster, R.

1977-01-01

Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

Third National Report on compliance with the Joint Convention Obligations

International Nuclear Information System (INIS)

2008-09-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. This report is the third one of its kind. It is published in accordance with Article 32 of the Joint Convention and presents the measures taken by France to meet each of her obligations set out in the Convention. The facilities and the radioactive materials covered by this Convention are quite diversified in nature and are controlled in France by different regulatory authorities. Above a specific threshold of radioactive content, a facility is referred to as a 'basic nuclear facility' (installation nucleaire de base - INB) and placed under the control of the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). Below that threshold and provided that the facility involved is subject to the nomenclature of classified facilities for other purposes than their radioactive materials, any facility may be considered as a 'classified facility on environmental-protection grounds' (installation classee pour la protection de l'environnement - ICPE) and placed under the control of the Ministry for the Environment. Facilities that contain only

SLIM (secondary emission monitor for low interception monitoring) an innovative non-destructive beam monitor for the extraction lines of a hadrontherapy centre

International Nuclear Information System (INIS)

Gibson, P.N.; Holzwarth, U.; Abbas, K.

2005-01-01

Real time monitoring of hadron therapy beam intensity and profile is a critical issue for the optimisation of dose delivery to carcinogenic tissue, patient safety and operation of the accelerator complex. For this purpose an innovative beam monitor, SLIM (Secondary electron emission for Low Interception Monitoring) is being developed in the framework of the EC-funded SUCIMA (Silicon Ultra-fast Cameras for electrons and gamma sources In Medical Application) project. The detector system is based on the secondary emission of electrons by a non-perturbative, sub-micron thick Al foil placed directly in the extracted beam path. The secondary electrons, accelerated by an electrostatic focusing system, are detected by a monolithic silicon position-sensitive sensor, which provides the beam intensity and its position with a precision of 1 mm at 10 kHz frame rate. The results of the laboratory tests of the first system prototype with thermoionic electrons emitted from a hot Tungsten wire are presented together with the measurements performed on a low intensity hadron beam at the Cyclotron of the Joint Research Centre in Ispra. (author)

Network analytical tool for monitoring global food safety highlights China.

Directory of Open Access Journals (Sweden)

Tamás Nepusz

Full Text Available BACKGROUND: The Beijing Declaration on food safety and security was signed by over fifty countries with the aim of developing comprehensive programs for monitoring food safety and security on behalf of their citizens. Currently, comprehensive systems for food safety and security are absent in many countries, and the systems that are in place have been developed on different principles allowing poor opportunities for integration. METHODOLOGY/PRINCIPAL FINDINGS: We have developed a user-friendly analytical tool based on network approaches for instant customized analysis of food alert patterns in the European dataset from the Rapid Alert System for Food and Feed. Data taken from alert logs between January 2003-August 2008 were processed using network analysis to i capture complexity, ii analyze trends, and iii predict possible effects of interventions by identifying patterns of reporting activities between countries. The detector and transgressor relationships are readily identifiable between countries which are ranked using i Google's PageRank algorithm and ii the HITS algorithm of Kleinberg. The program identifies Iran, China and Turkey as the transgressors with the largest number of alerts. However, when characterized by impact, counting the transgressor index and the number of countries involved, China predominates as a transgressor country. CONCLUSIONS/SIGNIFICANCE: This study reports the first development of a network analysis approach to inform countries on their transgressor and detector profiles as a user-friendly aid for the adoption of the Beijing Declaration. The ability to instantly access the country-specific components of the several thousand annual reports will enable each country to identify the major transgressors and detectors within its trading network. Moreover, the tool can be used to monitor trading countries for improved detector/transgressor ratios.

Evaluation of the fusion technology and safety programme of the Joint Research Centre (1980-85)

International Nuclear Information System (INIS)

Haines, M.; Cabibbo, N.; Crocker, J.G.; Lecomte, M.; Merz, E.

1986-01-01

The Joint Research Centre, Ispra, has been involved in fusion research since 1973. In July 1985 the Commission of European Communities - DG XII, following a policy of systematically evaluating its RandD activities, appointed a panel of external experts to evaluate the fusion technology and safety programme carried out at the Joint Research Centre. This report describes the work of the panel in evaluating the research performed by the JRC within the framework of its 1984-87 programme. The achievements of the previous programme, 1980-83, were also taken into consideration. The different research areas covered in the programme, i.e.: reactor studies, breeding blanket technology, structural materials studies, risk assessment and tritium laboratory studies, are described and a draft proposal for the period 1987-90 presented. The evaluation panel has been asked to assess the following aspects: the scientific and technical achievements of the programme, the contribution of the programme to the development of other Community policies, the role played by the JRC in the European fusion research (including NET) and in international collaborations such as INTOR. From its assessment the evaluation panel has made a series of recommendations for the current programme and for future work

Test and assessment method of Automotive Safety Systems (SSB) particularly to monitor traffic incidents

Science.gov (United States)

Pijanowski, B.; Łukjanow, S.; Burliński, R.

2016-09-01

The rapid development of telematics, particularly mobile telephony (GSM), wireless data transmission (GPRS) and satellite positioning (GPS) noticeable in the last decade, resulted in an almost unlimited growth of the possibilities for monitoring of mobile objects. These solutions are already widely used in the so-called “Intelligent Transport Systems” - ITS and affect a significant increase for road safety. The article describes a method of testing and evaluation of Car Safety Systems (Polish abbreviation - SSB) especially for monitoring traffic incidents, such as collisions and accidents. The algorithm of SSB testing process is also presented. Tests are performed on the dynamic test bench, part of which is movable platform with car security system mounted on it. Crash tests with a rigid obstacle are carried out instead of destructive attempts to crash test of the entire vehicle which is expensive. The tested system, depending on the simulated traffic conditions, is mounted in such a position and with the use of components, indicated by the manufacturer for the automotive safety system installation in a vehicle, for which it is intended. Then, the tests and assessments are carried out.

78 FR 47486 - Joint Failure on Continuous Welded Rail Track

Science.gov (United States)

2013-08-05

... evidence suggests that failed joint bars played a significant role in both derailments. This notice reminds... track maintenance instructions to remedy joint conditions that cause joint bars to fail and cause... preceding recommendations to help ensure the safety of the Nation's railroad employees and the public. FRA...

Monitoring System For Improving Radiation Safety Management

International Nuclear Information System (INIS)

Osovizky, A.; Paran, J.; Tal, N.; Ankry, N.; Ashkenazi, B.; Tirosh, D.; Marziano, R.; Chisin, R.

1999-01-01

Medi SMARTS (Medical Survey Mapping Automatic Radiation Tracing System), a gamma radiation monitoring system, was installed in a nuclear medicine department. In this paper the evaluation of the system's ability to improve radiation safety management is presented. The system is based on a state of the art software that continuously collects on line radiation measurements for display, analysis and logging. Radiation is measured by GM tubes; the signal is transferred to a data processing unit and then via an RS-485 communication line to a computer. The system automatically identifies the detector type and its calibration factor, thus providing compatibility, maintainability and versatility when changing detectors. Radiation levels are displayed on the nuclear medicine department map at six locations. The system has been operating continuously for more than one year, documenting abnormal events caused by routine operation or failure incidents. In cases where abnormal working conditions were encountered, an alarm message was sent automatically to the supervisor via his tele-pager. An interesting issue observed during the system evaluation, was the inability to distinguish between high radiation levels caused by proper routine operation and those caused by safety failure incidents. The solution included examination of two parameters, radiation levels as well as their duration period. A careful analysis of the historical data, applying the appropriated combined parameters determined for each location, verified that such a system can identify abnormal events, provide alarms to warn in case of incidents and improve standard operating procedures

33 CFR 183.554 - Fittings, joints, and connections.

Science.gov (United States)

2010-07-01

... (CONTINUED) BOATING SAFETY BOATS AND ASSOCIATED EQUIPMENT Fuel Systems Manufacturer Requirements § 183.554 Fittings, joints, and connections. Each fuel system fitting, joint, and connection must be arranged so that it can be reached for inspection, removal, or maintenance without removal of permanent boat structure. ...

Eighth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2000-01-01

From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

Development and application of the San Onofre safety monitor

International Nuclear Information System (INIS)

Hook, Thomas G.; Lee, Roger J.; Morgan, Thomas A.

2004-01-01

Halliburton NUS Corporation (NUS) has developed a risk-based configuration management software tool for use at Southern California Edison's San Onofre Nuclear Generating Station. The software, called the Safety Monitor, calculates an estimate of current plant core damage risk based upon the plant's current operating configuration (e.g., equipment operability, system operating alignments). All data is entered and displayed in a format easily understood by plant personnel. The plant hopes to use this tool to ensure that risk is minimized during plant operations and to identify situations in which current Technical Specifications can be optimized. Plant configuration data and out-of-service time data is also automatically collected. (author)

Addressing safety issues through a joint industry programme; Traiter des problemes de securite a travers un programme industriel commun

Energy Technology Data Exchange (ETDEWEB)

Pool, G.; Williams, T.P. [BG Technology (United Kingdom); Jones, A.M. [Health and Safety Executive (United Kingdom)

2000-07-01

In an increasingly fragmented gas market, the focus for national gas safety may not rest with one major utility or gas supplier but may be spread across many companies. There will also be many new organisations in a liberalized gas industry with varying views on the needs and benefits of safety related technology development but all agree there is a need to ensure that the good safety record of gas as a domestic fuel is maintained. The number of carbon monoxide (CO) incidents is not decreasing significantly despite an increased awareness of the problem. As a consequence, a two-year joint industry programme addressing issues related to carbon monoxide has been established, co-ordinated by BG Technology and supported by gas organisations, government agencies, manufacturers and suppliers across Europe and the World. The 2-year 2 pound million programme has been constructed as twelve separate projects addressing issues such as the reporting and analysis of domestic incidents, improved service or installation practice, CO alarm reliability and information dissemination. The paper gives results and achievements of the programme, through new techniques, standards, procedures or equipment and demonstrates how the gas industry can work together to meet common safety objectives. (authors)

Joint OSNR monitoring and modulation format identification in digital coherent receivers using deep neural networks.

Science.gov (United States)

Khan, Faisal Nadeem; Zhong, Kangping; Zhou, Xian; Al-Arashi, Waled Hussein; Yu, Changyuan; Lu, Chao; Lau, Alan Pak Tao

2017-07-24

We experimentally demonstrate the use of deep neural networks (DNNs) in combination with signals' amplitude histograms (AHs) for simultaneous optical signal-to-noise ratio (OSNR) monitoring and modulation format identification (MFI) in digital coherent receivers. The proposed technique automatically extracts OSNR and modulation format dependent features of AHs, obtained after constant modulus algorithm (CMA) equalization, and exploits them for the joint estimation of these parameters. Experimental results for 112 Gbps polarization-multiplexed (PM) quadrature phase-shift keying (QPSK), 112 Gbps PM 16 quadrature amplitude modulation (16-QAM), and 240 Gbps PM 64-QAM signals demonstrate OSNR monitoring with mean estimation errors of 1.2 dB, 0.4 dB, and 1 dB, respectively. Similarly, the results for MFI show 100% identification accuracy for all three modulation formats. The proposed technique applies deep machine learning algorithms inside standard digital coherent receiver and does not require any additional hardware. Therefore, it is attractive for cost-effective multi-parameter estimation in next-generation elastic optical networks (EONs).

U.S. Continuing Involvement with the Joint Convention

International Nuclear Information System (INIS)

Stewart, L.; Tonkay, D.; Regnier, E.; Schultheisz, D.; Gnugnoli, G.

2009-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) is an international convention, under the auspices of the International Atomic Energy Agency (IAEA). It is a companion to a suite of international conventions on nuclear safety and physical security, which serve to promote a global culture for the safe use of radioactive materials. The Joint Convention is an official international treaty, and as such, there are obligations on the part of the United States. Those nations having ratified the Joint Convention are designated as 'Contracting Parties.' Nations that are not IAEA Member States may also become Contracting Parties to the Joint Convention, although none has done so. The primary obligations are threefold. The first is to prepare a national report, which addresses the national safety program in radioactive waste management, spent nuclear fuel management, and disused sealed sources. As the U.S. prepares a national report, other Contracting Parties to the Joint Convention also prepare their national reports, which leads to the second obligation on the part of the Contracting Parties. This is the obligation to review other countries' national reports. The last specific obligation is to actively participate in the triennial peer review meeting, referred to as the Review Meeting of the Contracting Parties. The U.S. ratified the Joint Convention in 2003, just prior to the First Review Meeting of the Contracting Parties, and has participated fully therein in the ensuing Review Meetings. Because of the benefits in active participation, it is important for the U.S. to maintain its leadership role in promoting its ratification in the global setting, as well as in more focused regions. Because of the important benefits associated with active participation, the U.S. has strongly supported a Regional Conference Initiative outreach program to increase membership. To launch the Initiative, the U

Application of the Digital Image Technology in the Visual Monitoring and Prediction of Shuttering Construction Safety

Science.gov (United States)

Ummin, Okumura; Tian, Han; Zhu, Haiyu; Liu, Fuqiang

2018-03-01

Construction safety has always been the first priority in construction process. The common safety problem is the instability of the template support. In order to solve this problem, the digital image measurement technology has been contrived to support real-time monitoring system which can be triggered if the deformation value exceed the specified range. Thus the economic loss could be reduced to the lowest level.

Lightweight monitoring and control system for coal mine safety using REST style.

Science.gov (United States)

Cheng, Bo; Cheng, Xin; Chen, Junliang

2015-01-01

The complex environment of a coal mine requires the underground environment, devices and miners to be constantly monitored to ensure safe coal production. However, existing coal mines do not meet these coverage requirements because blind spots occur when using a wired network. In this paper, we develop a Web-based, lightweight remote monitoring and control platform using a wireless sensor network (WSN) with the REST style to collect temperature, humidity and methane concentration data in a coal mine using sensor nodes. This platform also collects information on personnel positions inside the mine. We implement a RESTful application programming interface (API) that provides access to underground sensors and instruments through the Web such that underground coal mine physical devices can be easily interfaced to remote monitoring and control applications. We also implement three different scenarios for Web-based, lightweight remote monitoring and control of coal mine safety and measure and analyze the system performance. Finally, we present the conclusions from this study and discuss future work. Copyright © 2014 ISA. Published by Elsevier Ltd. All rights reserved.

Riveted Lap Joints in Aircraft Fuselage Design, Analysis and Properties

CERN Document Server

Skorupa, Andrzej

2012-01-01

Fatigue of the pressurized fuselages of transport aircraft is a significant problem all builders and users of aircraft have to cope with for reasons associated with assuring a sufficient lifetime and safety, and formulating adequate inspection procedures. These aspects are all addressed in various formal protocols for creating and maintaining airworthiness, including damage tolerance considerations. In most transport aircraft, fatigue occurs in lap joints, sometimes leading to circumstances that threaten safety in critical ways. The problem of fatigue of lap joints has been considerably enlarged by the goal of extending aircraft lifetimes. Fatigue of riveted lap joints between aluminium alloy sheets, typical of the pressurized aircraft fuselage, is the major topic of the present book. The richly illustrated and well-structured chapters treat subjects such as: structural design solutions and loading conditions for fuselage skin joints; relevance of laboratory test results for simple lap joint specimens to rive...

Web of Things-Based Remote Monitoring System for Coal Mine Safety Using Wireless Sensor Network

OpenAIRE

Bo, Cheng; Xin, Cheng; Zhongyi, Zhai; Chengwen, Zhang; Junliang, Chen

2014-01-01

Frequent accidents have occurred in coal mine enterprises; therefore, raising the technological level of coal mine safety monitoring systems is an urgent problem. Wireless sensor networks (WSN), as a new field of research, have broad application prospects. This paper proposes a Web of Things- (WoT-) based remote monitoring system that takes full advantage of wireless sensor networks in combination with the CAN bus communication technique that abstracts the underground sensor data and capabili...

Applications of ZigBee Technology in the Safety Monitoring System of Low Gas Pipeline Transportation

Directory of Open Access Journals (Sweden)

Wei Deyu

2015-01-01

Full Text Available The existing safety monitoring system of low gas pipeline transportation establishes a wired communication network monitoring system mainly on the basis of industrial bus. It has problems such as large transmission signal attenuation, complex wiring, high-labor intensity, inconvenient installation and maintenance, high maintenance cost, and so on. Featuring low cost, power-saving, reliability, stability and flexibility, the wireless sensor network established by ZigBee wireless communication technology can realize the real-time all-dimensional dynamic monitoring on parameters of low gas pipeline transportation system and overcome the shortcomings and deficiencies of wired network system.

Overview of Recent Activities on Safety Culture and Human and Organizational Factors Carried Out at the Joint Research Centre of the European Commission

International Nuclear Information System (INIS)

Stručić, M.; Manna, G.

2016-01-01

The Institute for Energy and Transport (IET) of the Joint Research Centre (JRC) of the European Commission (EC) is since more than ten years active in the field of Safety Culture (SC) and Human and Organizational Factors (HOF). Several activities related to SC and HOF have been and are carried out in the frame of the EU Nuclear Safety Clearinghouse for Operating Experience Feedback (Clearinghouse). The Clearinghouse was established in 2008 to enhance nuclear safety through the lessons learned from NPP events, and to provide help in Operational Experience Feedback (OEF) process primarily to nuclear safety Regulatory Authorities and to their Technical Support Organizations within the EU. Additionally to these activities, during the Fukushima accident, Clearinghouse has been regularly providing reports on the status and progress of the accident to the EU Regulatory Authorities. Moreover, experts, selected from the JRC staffing, were directly engaged in the EU-wide risk and safety assessments of nuclear power plants known as “the Stress Tests”.

Catalogue of systems for the monitoring of working conditions relating to health and safety

NARCIS (Netherlands)

Prins, R.; Verboon, F.

1991-01-01

In this Catalogue a number of systems or instruments for Monitoring Working Conditions and workers Health and Safety have been described. The general aim of the project was three-fold: - to obtain an overall assessment of the existing instruments for identifying risk factors and working conditions

Developing Indicators for Monitoring and Evaluating Joint Management Effectiveness in Protected Areas in the Northern Territory, Australia

Directory of Open Access Journals (Sweden)

Arturo Izurieta

2011-09-01

We consider the effectiveness of a participatory process within the context of the relationships, capacities, skills, communication, and cross-cultural information sharing. We found that at the early stages of joint management, the partners mostly identify process indicators related to human and social capital assets. Cross-cultural engagement in the early stages of the monitoring and evaluation cycle is challenged by issues relating to communication, institutional and community capacities, representation, and flexibility in ways of working together while learning by doing. We conclude, however, that a participatory monitoring and evaluation approach in which partners agree equally on the identification of criteria and indicators to measure agreed management outcomes has the potential of improving equitable participation, decision making and working relationships, which in turn will lead to improved park management effectiveness and community outcomes.

Topical session proceedings of the 6. IGSC Meeting. The role of monitoring in a safety case

International Nuclear Information System (INIS)

2005-01-01

This report summarises the outcomes of a topical session focused on the role of monitoring in a safety case. It was held as part of the 6. plenary meeting of the IGSC. It was attended by 39 participants, representing waste management organisations and regulatory authorities from 15 NEA member countries, the IAEA and the European Commission. The main purpose of this topical session was to create a platform for exchanging views on the key monitoring issues of interest to build confidence in a safety case e.g. relationship with the post-closure phase, functions, requirements, and to determine to what extent the main actions are to be addressed by the IGSC on its ongoing activities on defining the elements of a safety case. The topical session was indeed mainly aimed at exchanging information on: - National strategies or programmes in NEA members' countries. Member countries have organisations planning their own strategy, but some are already, to some extend engaged in implementing monitoring activities, e.g. Posiva Oy, US-DOE-YM, Andra. - Feedback from international projects, e.g. the EC Thematic Network on 'The role of Monitoring in a Phased Approach to Geological Disposal of Radioactive Waste', and the IAEA programme of work. - The expectations of regulators, e.g. SKI. Part A of this document summarises the material orally presented and provides the main lessons drawn from the presentations and the discussions that followed them. The overheads presented are compiled without any further elaboration by the NEA Secretariat as Part B of the document. Part C gives the list of participants. The document as a whole provides a synthesis of current issues in monitoring of a deep geological disposal facility

The adaptive safety analysis and monitoring system

Science.gov (United States)

Tu, Haiying; Allanach, Jeffrey; Singh, Satnam; Pattipati, Krishna R.; Willett, Peter

2004-09-01

The Adaptive Safety Analysis and Monitoring (ASAM) system is a hybrid model-based software tool for assisting intelligence analysts to identify terrorist threats, to predict possible evolution of the terrorist activities, and to suggest strategies for countering terrorism. The ASAM system provides a distributed processing structure for gathering, sharing, understanding, and using information to assess and predict terrorist network states. In combination with counter-terrorist network models, it can also suggest feasible actions to inhibit potential terrorist threats. In this paper, we will introduce the architecture of the ASAM system, and discuss the hybrid modeling approach embedded in it, viz., Hidden Markov Models (HMMs) to detect and provide soft evidence on the states of terrorist network nodes based on partial and imperfect observations, and Bayesian networks (BNs) to integrate soft evidence from multiple HMMs. The functionality of the ASAM system is illustrated by way of application to the Indian Airlines Hijacking, as modeled from open sources.

FAO UN-REDD- INPE Joint Programme on Forest Monitoring Systems based on RS and GIS techniques

Science.gov (United States)

Jonckheere, I. G.; FAO UN-REDD MRV Team

2010-12-01

Capacity Development and Training for National Forest Monitoring Systems for Reducing Emissions from Deforestation and Forest Degradation in Developing Countries (REDD+) REDD+, which stands for ’Reducing Emissions from Deforestation and Forest Degradation in Developing Countries’ - is an effort to create a financial value for the carbon stored in forests, offering incentives for developing countries to reduce emissions from forested lands and invest in low-carbon paths to sustainable development. The UN-REDD Programme, a collaborative partnership between FAO, UNDP and UNEP launched in September 2008, supports countries to develop capacity to REDD+ and to implement a future REDD+ mechanism in a post-2012 climate regime. The programme works at both the national and global scale, through support mechanisms for country-driven REDD strategies and international consensus-building on REDD+ processes. The UN-REDD Programme gathers technical teams from around the world to develop common approaches, analyses and guidelines on issues such as measurement, reporting and verification (MRV) of carbon emissions and flows, remote sensing, and greenhouse gas inventories. Within the partnership, FAO supports countries on technical issues related to forestry and the development of cost effective and credible MRV processes for emission reductions. While at the international level, it fosters improved guidance on MRV approaches, including consensus on principles and guidelines for MRV and training programmes. It provides guidance on how best to design and implement REDD+, to ensure that forests continue to provide multiple benefits for livelihoods and biodiversity to societies while storing carbon at the same time. Other areas of work include national forest assessments and monitoring of in-country policy and institutional change. FAO and INPE (Brazilian Space Agency) have joint forces through a MoU signed last year in Copenhagen. A major joint programme has been agreed upon to set

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Development of Information Support of the Automated System for Monitoring the State of the Gas Transportation System’s Industrial Safety

Directory of Open Access Journals (Sweden)

Ruslan Skrynkovskyy

2017-08-01

Full Text Available The purpose of the article is to developing the information security of the automated system for monitoring the state of industrial safety of the gas transportation system within the framework of the safety management system, which will enable timely and objective detection of adverse accident hazards (hazardous events and taking the necessary specific measures to eliminate them and operate the gas transport system safely. It is proved that the basis of the information provision of the automated system for monitoring the state of the industrial safety of the gas transmission system is a methodology that includes the following basic procedures: identifying hazards; qualitative and quantitative assessment of emergencies; establishing of unacceptable (unallowable risks and their introduction to the information base (register of unacceptable risks of objects of the gas transportation system; comprehensive assessment and certification of the state of industrial safety of objects of the gas transportation system; identification of effective, productive (efficient risk management measures. The prospect of further research in this area is the development and implementation of an automated system for monitoring the state of industrial safety of the objects of the gas transmission system based on the results of the research (of the submitted information provision.

Importance of modeling beam-column joints for seismic safety of reinforced concrete structures

International Nuclear Information System (INIS)

Sharma, Akanshu; Reddy, G.R.; Vaze, K.K.; Eligehausen, R.; Hofmann, J.

2011-01-01

Almost all structures, except the containment building, in a NPP can be classified as reinforced concrete (RC) framed structures. In case of such structures subjected to seismic loads, beam-column joints are recognized as the critical and vulnerable zone. During an earthquake, the global behavior of the structure is highly governed by the behavior of the joints. If the joints behave in a ductile manner, the global behavior generally will be ductile, whereas if the joints behave in a brittle fashion then the structure will display a brittle behavior. The joints of old and non-seismically detailed structures are more vulnerable and behave poorly under the earthquakes compared to the joints of new and seismically detailed structures. Modeling of these joint regions is very important for correct assessment of the seismic performance of the structures. In this paper, it is shown with the help of a recently developed joint model that not modeling the inelastic behavior of the joints can lead to significantly misleading and unsafe results in terms of the performance assessment of the structures under seismic loads. Comparison of analytical and experimental results is shown for two structures, tested under lateral monotonic seismic pushover loads. It is displayed that the model can predict the inelastic seismic response of structures considering joint distortion with high accuracy by little extra effort in modeling. (author)

Measurement and monitoring of safety: impact and challenges of putting a conceptual framework into practice.

Science.gov (United States)

Chatburn, Eleanor; Macrae, Carl; Carthey, Jane; Vincent, Charles

2018-03-06

The Measurement and Monitoring of Safety Framework provides a conceptual model to guide organisations in assessing safety. The Health Foundation funded a large-scale programme to assess the value and impact of applying the Framework in regional and frontline care settings. We explored the experiences and reflections of key participants in the programme. The study was conducted in the nine healthcare organisations in England and Scotland testing the Framework (three regional improvement bodies, six frontline settings). Post hoc interviews with clinical and managerial staff were analysed using template analysis. Participants reported that the Framework promoted a substantial shift in their thinking about how safety is actively managed in their environment. It provided a common language, facilitated a more inquisitive approach and encouraged a more holistic view of the components of safety. These changes in conceptual understanding, however, did not always translate into broader changes in practice, with many sites only addressing some aspects of the Framework. One of the three regions did embrace the Framework in its entirety and achieved wider impact with a range of interventions. This region had committed leaders who took time to fully understand the concepts, who maintained a flexible approach to exploring the utility of the Framework and who worked with frontline staff to translate the concepts for local settings. The Measuring and Monitoring of Safety Framework has the potential to support a broader and richer approach to organisational safety. Such a conceptually based initiative requires both committed leaders who themselves understand the concepts and more time to establish understanding and aims than might be needed in a standard improvement programme. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

Energy Technology Data Exchange (ETDEWEB)

Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I. [National Institute of Cryogenics and Isotopes Technologies, Ramnicu Valcea (Romania)

2006-07-01

The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

International Nuclear Information System (INIS)

Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I.

2006-01-01

The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

Safety Evaluation of an Automated Remote Monitoring System for Heart Failure in an Urban, Indigent Population.

Science.gov (United States)

Gross-Schulman, Sandra; Sklaroff, Laura Myerchin; Hertz, Crystal Coyazo; Guterman, Jeffrey J

2017-12-01

Heart Failure (HF) is the most expensive preventable condition, regardless of patient ethnicity, race, socioeconomic status, sex, and insurance status. Remote telemonitoring with timely outpatient care can significantly reduce avoidable HF hospitalizations. Human outreach, the traditional method used for remote monitoring, is effective but costly. Automated systems can potentially provide positive clinical, fiscal, and satisfaction outcomes in chronic disease monitoring. The authors implemented a telephonic HF automated remote monitoring system that utilizes deterministic decision tree logic to identify patients who are at risk of clinical decompensation. This safety study evaluated the degree of clinical concordance between the automated system and traditional human monitoring. This study focused on a broad underserved population and demonstrated a safe, reliable, and inexpensive method of monitoring patients with HF.

Configuration of risk monitor system by plant defense-in-depth risk monitor and reliability monitor

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu; Lind Morten; Yang Ming; Hashim Muhammad; Zhang Zhijian

2012-01-01

A new method of risk monitor system of a nuclear power plant has been proposed from the aspect by what degree of safety functions incorporated in the plant system is maintained by multiple barriers of defense-in-depth (DiD). Wherein, the central idea is plant DiD risk monitor and reliability monitor derived from the five aspects of (1) design principle of nuclear safety based on DiD concept, (2) definition of risk and risk to be monitored, (3) severe accident phenomena as major risk, (4) scheme of risk ranking, and (5) dynamic risk display. In this paper, the overall frame of the proposed risk monitor system is summarized and the detailed discussion is made on major items such as definition of risk and risk ranking, anatomy of fault occurrence, two-layer configuration of risk monitor, how to configure individual elements of plant DiD risk monitor, and lastly how to apply for a PWR safety system. (author)

Wearable human body joint and posture measuring system

NARCIS (Netherlands)

Dunias, P.; Gransier, R.; Jin, A.; Statham, A.; Willems, P.

2011-01-01

In many medical applications, especially the orthopaedic setting, ambulatory, monitoring of human joint angles could be of substantial value to improving rehabilitation strategies and unravelling the pathomechanics of many degenerative joint diseases (e.g. knee osteoarthritis). With the ageing of

Analysis of NSTX TF Joint Voltage Measurements

International Nuclear Information System (INIS)

Woolley R

2005-01-01

This report presents findings of analyses of recorded current and voltage data associated with 72 electrical joints operating at high current and high mechanical stress. The analysis goal was to characterize the mechanical behavior of each joint and thus evaluate its mechanical supports. The joints are part of the toroidal field (TF) magnet system of the National Spherical Torus Experiment (NSTX) pulsed plasma device operating at the Princeton Plasma Physics Laboratory (PPPL). Since there is not sufficient space near the joints for much traditional mechanical instrumentation, small voltage probes were installed on each joint and their voltage monitoring waveforms have been recorded on sampling digitizers during each NSTX ''shot''

Overcoming regulatory challenges in the development of companion diagnostics for monitoring and safety.

Science.gov (United States)

Shimazawa, Rumiko; Ikeda, Masayuki

2016-03-01

Concurrent development and co-approval of a companion diagnostic (CDx) with a corresponding drug is ideal, but often unfeasible. Because of limited exposure to a drug in clinical trials, crucial information on safety is sometimes revealed only after approval. Therefore, a CDx for monitoring/safety is often developed after approval of a corresponding drug. However, regulatory guidance is insufficient if contemporaneous development is not possible, thereby leaving plenty of opportunities for improvement with respect to pharmacovigilance and retrospective validation of the CDx. Furthermore, global harmonization of guidance on how to incorporate new scientific information from retrospective analyses of biomarkers should lead to the establishment of more evidence for the development of CDx for approved drugs.

Assessment of the global trigger tool to measure, monitor and evaluate pateint safety in cancer patients

DEFF Research Database (Denmark)

Otto Mattsson, Thea; Lehmann-Knudsen, Janne; Lauritsen, Jens M

2013-01-01

BACKGROUND: Countries around the world are currently aiming to improve patient safety by means of the Institute for Healthcare Improvement global trigger tool (GTT), which is considered a valid tool for evaluating and measuring patient safety within organisations. So far, only few data....... RESULTS: Only 31% of adverse events (AE) were identified by both teams, and further differences in categorisation of identical events was found. Moderate interrater agreement (κ=0.45) between teams gave rise to different conclusions on the patient safety process when monitoring using SPC charts. The Bland......-Altman plot suggests little systematic error but large random error. CONCLUSIONS: Review teams may identify different AE and reach different conclusions on the safety process when using the GTT on identical charts. Tracking true change in the safety level is difficult due to measurement error of the GTT...

A risk stratification algorithm using non-invasive respiratory volume monitoring to improve safety when using post-operative opioids in the PACU.

Science.gov (United States)

Voscopoulos, Christopher; Theos, Kimberly; Tillmann Hein, H A; George, Edward

2017-04-01

Late detection of respiratory depression in non-intubated patients compromises patient safety. SpO 2 is a lagging indicator of respiratory depression and EtCO 2 has proven to be unreliable in non-intubated patients. A decline in minute ventilation (MV) is the earliest sign of respiratory depression. A non-invasive respiratory volume monitor (RVM) that provides accurate, continuous MV measurements enables clinicians to predict and quantify respiratory compromise. For this observational study, practitioners were blinded to the RVM measurements and pain management followed the usual routine. Patients were stratified by their MV on PACU admission and classified as "At-Risk" or "Not-At-Risk," with progression to "Low MV" status following opioids assessed for each category. The purpose was to determine if stratifying based on MV on PACU arrival could identify patients at higher risk for respiratory depression. Ability to identify in advance patients at higher risk for respiratory depression following standard opioid dosing would drive changes in pain management and improve patient care. RVM and opioid administration data from 150 PACU patients following elective joint-replacement surgery were collected in an observational study. "Predicted" MV (MV PRED ) and "Percent Predicted" (MV MEASURED /MV PRED  × 100 %) were calculated for each patient using standard formulas. Prior to opioid administration, patients were classified as either "Not-At-Risk" (MV ≥ 80 % MV PRED ) or "At-Risk" (MV safety across the continuum of care.

Joint made of shape memory alloy

International Nuclear Information System (INIS)

Amano, Kazuo; Enomoto, Kunio

1998-01-01

The present invention provides a joint which is less loosen even if it is used under a circumference undergoing heat cycles such as in a nuclear power plant. Namely, a liner shape has a structure different between the right-to-left, which is different from existent right and left symmetrical shape. A groove is formed on the side of pipeline to be connected, and upon joint connection, the liner is pushed into the groove formed on the pipeline to connect them by the force caused upon transformation of the shape memory alloy. In the joint having such a structure, the clamping force of the joint is less reduced by the effects of heat cycles. Even when the clamping force is reduced by some or other causes, the joint is not dropped off from the pipeline. Even when the joint made of a shape memory alloy of a type using a liner is used as a joint for connecting longitudinal pipelines of a nuclear power plant, the reliability and the safety can be maintained. (I.S.)

Systems for the monitoring of working conditions relating to health and safety : extensive descriptions : Belgium, Germany, Luxembourg, The Netherlands

NARCIS (Netherlands)

Prins, R.; Verboon, F.

1991-01-01

This report contains the extensive descriptions of (some of) the monitoring systems on health and safety in use in the Benelux countries and Germany. The project of which this report is a part aimed at gathering information on monitoring systems throughout the EC member states.

Nuclear materials facility safety initiative

International Nuclear Information System (INIS)

Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

2000-01-01

Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

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

International Nuclear Information System (INIS)

2009-03-01

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

A minimal architecture for joint action

DEFF Research Database (Denmark)

Vesper, Cordula; Butterfill, Stephen; Knoblich, Günther

2010-01-01

What kinds of processes and representations make joint action possible? In this paper we suggest a minimal architecture for joint action that focuses on representations, action monitoring and action prediction processes, as well as ways of simplifying coordination. The architecture spells out...... minimal requirements for an individual agent to engage in a joint action. We discuss existing evidence in support of the architecture as well as open questions that remain to be empirically addressed. In addition, we suggest possible interfaces between the minimal architecture and other approaches...... to joint action. The minimal architecture has implications for theorizing about the emergence of joint action, for human-machine interaction, and for understanding how coordination can be facilitated by exploiting relations between multiple agents’ actions and between actions and the environment....

Ward based community road safety performance benchmarking, monitoring and intervention programmes in the City of Johannesburg

CSIR Research Space (South Africa)

Ribbens, H

2008-07-01

Full Text Available benchmarking, monitoring and intervention programme. Community road safety needs in the respective wards are articulated through the ward councillor. The rationale is that the community exactly knows where these problem areas are, because they suffer as a...

Evaluation of remote monitoring at the Oak Ridge HEU storage vault -- First thoughts and final application

International Nuclear Information System (INIS)

Sheely, K.B.; Whitaker, J.M.

1996-01-01

Remote monitoring provides a more timely and comprehensive way to meet national and international requirements for monitoring nuclear material inventories. Unattended monitoring technologies could be used to meet national needs for nuclear material safety, protection, control and accountability. Unattended systems possessing a remote data transmission capability could be used to meet international requirements for nuclear material safeguards and transparency. Even though more enhancements are required to improve system reliability, remote monitoring''s future potential seems great. The key questions are: (1) how will remote monitoring systems be used (configuration and operation); (2) how effective will the system be (vs. current activities); and (3) how much will it cost. This paper provides preliminary answers to these questions based on the experience gained from a joint IAEA-United States Support Program (USSP) task to evaluate remote monitoring at the Oak Ridge HEU Storage vault. This paper also draws on experience gained from US involvement in other remote monitoring projects

Drug Safety

Science.gov (United States)

... over-the-counter drug. The FDA evaluates the safety of a drug by looking at Side effects ... clinical trials The FDA also monitors a drug's safety after approval. For you, drug safety means buying ...

An advanced joint inversion system for CO₂ storage modeling with large date sets for characterization and real-time monitoring-enhancing storage performance and reducing failure risks under uncertainties

Energy Technology Data Exchange (ETDEWEB)

Kitanidis, Peter [Stanford Univ., CA (United States)

2016-04-30

As large-scale, commercial storage projects become operational, the problem of utilizing information from diverse sources becomes more critically important. In this project, we developed, tested, and applied an advanced joint data inversion system for CO₂ storage modeling with large data sets for use in site characterization and real-time monitoring. Emphasis was on the development of advanced and efficient computational algorithms for joint inversion of hydro-geophysical data, coupled with state-of-the-art forward process simulations. The developed system consists of (1) inversion tools using characterization data, such as 3D seismic survey (amplitude images), borehole log and core data, as well as hydraulic, tracer and thermal tests before CO₂ injection, (2) joint inversion tools for updating the geologic model with the distribution of rock properties, thus reducing uncertainty, using hydro-geophysical monitoring data, and (3) highly efficient algorithms for directly solving the dense or sparse linear algebra systems derived from the joint inversion. The system combines methods from stochastic analysis, fast linear algebra, and high performance computing. The developed joint inversion tools have been tested through synthetic CO₂ storage examples.

Office Visits to Monitor Stimulant Medication Safety and Efficacy: Recommended Care.

Science.gov (United States)

Zima, Bonnie T; Norquist, Grayson S; Altchuler, Steven I; Behrens, Jacob; Iles-Shih, Matthew D; Ng, Yiu Kee Warren; Schaepper, Mary Ann

2018-06-01

The clinical guidance based on the research article, "Specific Components of Pediatricians' Medication-Related Care Predict Attention-Deficit/Hyperactivity Disorder Improvement," published in the June 2017 issue, 1 might be premature. The authors, Epstein et al., suggest that "Physicians do not need to necessarily rely on office visits to monitor medication response and side effects in the week(s) after initially prescribing medication, but instead could use phone calls or email correspondence to check in with the family" (p. 489). However, this advice has the potential to be misinterpreted that phone or email contact is acceptable clinical practice to monitor stimulant medication safety and efficacy, especially during the maintenance phase. It also could be erroneously interpreted that phone or email contact is sufficient for follow-up care for children receiving medication treatment for attention-deficit/hyperactivity disorder (ADHD) for national quality measures. Copyright © 2018 American Academy of Child and Adolescent Psychiatry. Published by Elsevier Inc. All rights reserved.

CSNI collective statement on support facilities for existing and advanced reactors. The function of OECD/Nea joint projects Nea committee on the safety of nuclear installations (CSNI)

International Nuclear Information System (INIS)

2008-01-01

The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide. Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritize technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors. This statement constitutes a reference for future CSNI activities and for safety authorities, R and D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area. (author)

Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

International Nuclear Information System (INIS)

Sneve, M.K.

2013-01-01

The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

Energy Technology Data Exchange (ETDEWEB)

Sneve, M.K.

2013-03-01

The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

Temporomandibular Joint Septic Arthritis

Directory of Open Access Journals (Sweden)

Gianfranco Frojo, MD

2018-01-01

Full Text Available Summary:. Infection of the temporomandibular joint (TMJ is a rare pediatric condition resulting from the introduction of pathogens into the joint by hematogenous seeding, local extension, or trauma. Early recognition of the typical signs and symptoms including fever, trismus, preauricular swelling, and TMJ region tenderness are critical in order to initiate further evaluation and prevent feared complications of fibrosis, ankylosis, abnormal facial structure, or persistence of symptoms. Contrast-enhanced computed tomography with ancillary laboratory analysis including erythrocyte sedimentation rate, C-reactive protein, and white blood cell count are beneficial in confirming the suspected diagnosis and monitoring response to therapy. Initial intervention should include empiric parenteral antibiotics, early mandibular mobilization, and joint decompression to provide synovial fluid for analysis including cultures. This report describes a case of TMJ bacterial arthritis in a healthy 6-year-old male who was promptly treated nonsurgically with intravenous antibiotics and localized needle joint decompression with return to normal function after completion of oral antibiotics and physical therapy.

Indicators of safety culture - selection and utilization of leading safety performance indicators

Energy Technology Data Exchange (ETDEWEB)

Reiman, Teemu; Pietikaeinen, Elina (VTT, Technical Research Centre of Finland (Finland))

2010-03-15

Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

Indicators of safety culture - selection and utilization of leading safety performance indicators

International Nuclear Information System (INIS)

Reiman, Teemu; Pietikaeinen, Elina

2010-03-01

Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

Seventh ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Raeder, J.; Gordon, C.

2000-01-01

From February 15 to 18, 2000, the Seventy Technical Meeting on Safety and Environment was held at the Garching Joint Work Site which now hosts the Safety, Environment and Health Group of the ITER Joint Central Team. At this meeting, safety experts from the Home Teams worked with the SEHG members on reviews and agreements on the contents of GSSR and on the tasks and the schedule for the production of GSSR as well as the design information to be used and for the analyses to be done

The challenges in monitoring and preventing patient safety incidents for people with intellectual disabilities in NHS acute hospitals: evidence from a mixed-methods study.

Science.gov (United States)

Tuffrey-Wijne, Irene; Goulding, Lucy; Gordon, Vanessa; Abraham, Elisabeth; Giatras, Nikoletta; Edwards, Christine; Gillard, Steve; Hollins, Sheila

2014-09-24

There has been evidence in recent years that people with intellectual disabilities in acute hospitals are at risk of preventable deterioration due to failures of the healthcare services to implement the reasonable adjustments they need. The aim of this paper is to explore the challenges in monitoring and preventing patient safety incidents involving people with intellectual disabilities, to describe patient safety issues faced by patients with intellectual disabilities in NHS acute hospitals, and investigate underlying contributory factors. This was a 21-month mixed-method study involving interviews, questionnaires, observation and monitoring of incident reports to assess the implementation of recommendations designed to improve care provided for patients with intellectual disabilities and explore the factors that compromise or promote patient safety. Six acute NHS Trusts in England took part. Data collection included: questionnaires to clinical hospital staff (n = 990); questionnaires to carers (n = 88); interviews with: hospital staff including senior managers, nurses and doctors (n = 68) and carers (n = 37); observation of in-patients with intellectual disabilities (n = 8); monitoring of incident reports (n = 272) and complaints involving people with intellectual disabilities. Staff did not always readily identify patient safety issues or report them. Incident reports focused mostly around events causing immediate or potential physical harm, such as falls. Hospitals lacked effective systems for identifying patients with intellectual disabilities within their service, making monitoring safety incidents for this group difficult.The safety issues described by the participants were mostly related to delays and omissions of care, in particular: inadequate provision of basic nursing care, misdiagnosis, delayed investigations and treatment, and non-treatment decisions and Do Not Attempt Cardiopulmonary Resuscitation (DNACPR) orders. The events leading to avoidable harm

The IAEA Safety Regime for Decommissioning

International Nuclear Information System (INIS)

Bell, M.J.

2002-01-01

Full text of publication follows: The International Atomic Energy Agency is developing an international framework for decommissioning of nuclear facilities that consists of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, and a hierarchy of Safety Standards applicable to decommissioning. The Joint Convention entered into force on 18 June 2001 and as of December 2001 had been ratified by 27 IAEA Member States. The Joint Convention contains a number of articles dealing with planning for, financing, staffing and record keeping for decommissioning. The Joint Convention requires Contracting Parties to apply the same operational radiation protection criteria, discharge limits and criteria for controlling unplanned releases during decommissioning that are applied during operations. The IAEA has issued Safety Requirements document and three Safety Guides applicable to decommissioning of facilities. The Safety Requirements document, WS-R-2, Pre-disposal Management of Radioactive Waste, including Decommissioning, contains requirements applicable to regulatory control, planning and funding, management of radioactive waste, quality assurance, and environmental and safety assessment of the decommissioning process. The three Safety Guides are WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, WS-G-2.2, Decommissioning of Medical, Industrial and Research Facilities, an WS-G-2.4, Decommissioning of Nuclear Fuel Cycle Facilities. They contain guidance on how to meet the requirements of WS-R-2 applicable to decommissioning of specific types of facilities. These Standards contain only general requirements and guidance relative to safety assessment and do not contain details regarding the content of the safety case. More detailed guidance will be published in future Safety Reports currently in preparation within the Waste Safety Section of the IAEA. Because much material arising during the decommissioning

Radiation Safety in Industrial Radiography. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

ASIC-based design of NMR system health monitor for mission/safety-critical applications.

Science.gov (United States)

Balasubramanian, P

2016-01-01

N-modular redundancy (NMR) is a generic fault tolerance scheme that is widely used in safety-critical circuit/system designs to guarantee the correct operation with enhanced reliability. In passive NMR, at least a majority (N + 1)/2 out of N function modules is expected to operate correctly at any time, where N is odd. Apart from a conventional realization of the NMR system, it would be useful to provide a concurrent indication of the system's health so that an appropriate remedial action may be initiated depending upon an application's safety criticality. In this context, this article presents the novel design of a generic NMR system health monitor which features: (i) early fault warning logic, that is activated upon the production of a conflicting result by even one output of any arbitrary function module, and (ii) error signalling logic, which signals an error when the number of faulty function modules unfortunately attains a majority and the system outputs may no more be reliable. Two sample implementations of NMR systems viz. triple modular redundancy and quintuple modular redundancy with the proposed system health monitoring are presented in this work, with a 4-bit ALU used for the function modules. The simulations are performed using a 32/28 nm CMOS process technology.

Initial Demonstration of the Real-Time Safety Monitoring Framework for the National Airspace System Using Flight Data

Science.gov (United States)

Roychoudhury, Indranil; Daigle, Matthew; Goebel, Kai; Spirkovska, Lilly; Sankararaman, Shankar; Ossenfort, John; Kulkarni, Chetan; McDermott, William; Poll, Scott

2016-01-01

As new operational paradigms and additional aircraft are being introduced into the National Airspace System (NAS), maintaining safety in such a rapidly growing environment becomes more challenging. It is therefore desirable to have an automated framework to provide an overview of the current safety of the airspace at different levels of granularity, as well an understanding of how the state of the safety will evolve into the future given the anticipated flight plans, weather forecast, predicted health of assets in the airspace, and so on. Towards this end, as part of our earlier work, we formulated the Real-Time Safety Monitoring (RTSM) framework for monitoring and predicting the state of safety and to predict unsafe events. In our previous work, the RTSM framework was demonstrated in simulation on three different constructed scenarios. In this paper, we further develop the framework and demonstrate it on real flight data from multiple data sources. Specifically, the flight data is obtained through the Shadow Mode Assessment using Realistic Technologies for the National Airspace System (SMART-NAS) Testbed that serves as a central point of collection, integration, and access of information from these different data sources. By testing and evaluating using real-world scenarios, we may accelerate the acceptance of the RTSM framework towards deployment. In this paper we demonstrate the framework's capability to not only estimate the state of safety in the NAS, but predict the time and location of unsafe events such as a loss of separation between two aircraft, or an aircraft encountering convective weather. The experimental results highlight the capability of the approach, and the kind of information that can be provided to operators to improve their situational awareness in the context of safety.

Flat H Frangible Joint Evolution

Science.gov (United States)

Diegelman, Thomas E.; Hinkel, Todd J.; Benjamin, Andrew; Rochon, Brian V.; Brown, Christopher W.

2016-01-01

Space vehicle staging and separation events require pyrotechnic devices. They are single-use mechanisms that cannot be tested, nor can failure-tolerant performance be demonstrated in actual flight articles prior to flight use. This necessitates the implementation of a robust design and test approach coupled with a fully redundant, failure-tolerant explosive mechanism to ensure that the system functions even in the event of a single failure. Historically, NASA has followed the single failure-tolerant (SFT) design philosophy for all human-rated spacecraft, including the Space Shuttle Program. Following the end of this program, aerospace companies proposed building the next generation human-rated vehicles with off-the-shelf, non-redundant, zero-failure-tolerant (ZFT) separation systems. Currently, spacecraft and launch vehicle providers for both the Orion and Commercial Crew Programs (CCPs) plan to deviate from the heritage safety approach and NASA's SFT human rating requirements. Both programs' partners have base-lined ZFT frangible joints for vehicle staging and fairing separation. These joints are commercially available from pyrotechnic vendors. Non-human-rated missions have flown them numerous times. The joints are relatively easy to integrate structurally within the spacecraft. In addition, the separation event is debris free, and the resultant pyro shock is lower than that of other design solutions. It is, however, a serious deficiency to lack failure tolerance. When used for critical applications on human-rated vehicles, a single failure could potentially lead to loss of crew (LOC) or loss of mission (LOM)). The Engineering and Safety & Mission Assurance directorates within the NASA Johnson Space Center took action to address this safety issue by initiating a project to develop a fully redundant, SFT frangible joint design, known as the Flat H. Critical to the ability to retrofit on launch vehicles being developed, the SFT mechanisms must fit within the same

Diagnosis function of safety status in the safety parameter display system (SPDS)

International Nuclear Information System (INIS)

Zhang Yuanfang

1993-04-01

An automatic diagnosis function of safety status for nuclear power plant adopted in the SPDS is introduced. To guarantee diagnosis diversification, two diagnosis criteria of a design basis accident monitoring and a critical safety function monitoring used in plant emergency operation are provided. As an extensive function, a parameter deviation monitoring used in plant normal operation is also provided

An Online Risk Monitor System (ORMS) to Increase Safety and Security Levels in Industry

International Nuclear Information System (INIS)

Zubair, M; Ur Rahman, Khalil; Ul Hassan, Mehmood

2013-01-01

The main idea of this research is to develop an Online Risk Monitor System (ORMS) based on Living Probabilistic Safety Assessment (LPSA). The article highlights the essential features and functions of ORMS. The basic models and modules such as, Reliability Data Update Model (RDUM), running time update, redundant system unavailability update, Engineered Safety Features (ESF) unavailability update and general system update have been described in this study. ORMS not only provides quantitative analysis but also highlights qualitative aspects of risk measures. ORMS is capable of automatically updating the online risk models and reliability parameters of equipment. ORMS can support in the decision making process of operators and managers in Nuclear Power Plants

An Online Risk Monitor System (ORMS) to Increase Safety and Security Levels in Industry

Science.gov (United States)

Zubair, M.; Rahman, Khalil Ur; Hassan, Mehmood Ul

2013-12-01

The main idea of this research is to develop an Online Risk Monitor System (ORMS) based on Living Probabilistic Safety Assessment (LPSA). The article highlights the essential features and functions of ORMS. The basic models and modules such as, Reliability Data Update Model (RDUM), running time update, redundant system unavailability update, Engineered Safety Features (ESF) unavailability update and general system update have been described in this study. ORMS not only provides quantitative analysis but also highlights qualitative aspects of risk measures. ORMS is capable of automatically updating the online risk models and reliability parameters of equipment. ORMS can support in the decision making process of operators and managers in Nuclear Power Plants.

Parent-adolescent joint projects involving leisure time and activities during the transition to high school.

Science.gov (United States)

Marshall, Sheila K; Young, Richard A; Wozniak, Agnieszka; Lollis, Susan; Tilton-Weaver, Lauree; Nelson, Margo; Goessling, Kristen

2014-10-01

Leisure research to date has generally overlooked planning and organizing of leisure time and activities between parents and adolescents. This investigation examined how a sample of Canadian adolescents and their parents jointly constructed and acted on goals related to adolescents' leisure time during the move from elementary to high school. Using the Qualitative Action-Project Method, data were collected over an 8-10 month period from 26 parent-adolescent dyads located in two urban sites, through video-taped conversations about leisure time, video recall interviews, and telephone monitoring interviews. Analysis of the data revealed that the joint projects of the 26 dyads could be grouped into three clusters: a) governance transfer or attempts to shift, from parent to adolescent, responsibility over academic demands, organizing leisure time, and safety with peers, b) balancing extra-curricular activities with family life, academics, and social activities, and c) relationship adjustment or maintenance. Crown Copyright © 2014. Published by Elsevier Ltd. All rights reserved.

Real-time environmental monitoring at the Japan Nuclear Cycle Development Institute O-arai Engineering Center. Using the internet to promote safety and environmental transparency

International Nuclear Information System (INIS)

Motomatsu, Sheila; Nakashima Inoue, Naoko

2000-12-01

The report documents the results of an effort at the Japan Nuclear Cycle Development Institute O-arai Engineering Center (JNC/OEC) to provide via the Internet, in real-time, environmental monitoring data to promote safety and environmental transparency. Provided in Japanese as well as in English, the Internet site provides assurance that OEC nuclear operations are being conducted in a manner that is safe to both people in the surrounding area and the environment. This work conducted by Environmental Monitoring Team of the OEC Safety Administration Section fulfilled the assignment to release data real-time via the Internet tasked by the Information Disclosure Section of the JNC Headquarters Public Relations Division. The work conducted by the visiting exchange scientist fulfilled the experimental portion of Action Sheet 34 of the Agreement between JNC and DOE for Cooperation in Research and Development Concerning Nuclear Material Control and Accounting Measures for Safeguards and Nonproliferation. In Japan, the project for Action Sheet 34 Personnel Exchange on Remote Monitoring and Transparency' entailed both a study and an experiment on how remote monitoring technologies can be used to promote nonproliferation, environmental and safety transparency. Environmental airborne radionuclide monitoring falls under the definition of remote monitoring technology more broadly defined as 'remotely accessed unattended monitoring system technology'. (author)

Development of a web based monitoring system for safety and activity analysis in operating theatres.

Science.gov (United States)

Frosini, Francesco; Miniati, Roberto; Avezzano, Paolo; Cecconi, Giulio; Dori, Fabrizio; Gentili, Guido Biffi; Belardinelli, Andrea

2016-01-01

The management and the monitoring of the operating rooms on the part of the general management have the objective of optimizing their use and maximizing the internal safety. The expenses owed to their safe use represent, besides reimbursements coming from the surgical activity, important factors for the analysis of the medical facility. Given that it is not possible to reduce the safety, it is necessary to develop supporting systems with the aim to enhance and optimize the use of the rooms. The developed analysis model of the operating rooms in this study is based on the specific performance indicators and allows the effective monitoring of both the parameters that influence the safety (environmental, microbiological parameters) and those that influence the efficiency of the usage (employment rate, delays, necessary formalities, etc.). This allows you to have a systematic dashboard on hand for all of the OTs and, thus, organize the intervention schedules and more appropriate improvements. A monitoring dashboard has been achieved, accessible from any platform and any device, capable of aggregating hospital information. The undertaken organizational modifications, through the use of the dashboard, have allowed for an average annual savings of 29.52 minutes per intervention and increase the use of the ORs of 5%. The increment of the employment rate and the optimization of the operating room have allowed for savings of around $299,88 for every intervention carried out in 2013, corresponding to an annual savings of $343,362,60. Integration dashboards, as the one proposed in this study as a prototype, represent a governance model of economically sustainable healthcare systems capable of guiding the hospital management in the choices and in the implementation of the most efficient organizational modifications.

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Iranian Joint Registry(Iranian National Hip and Knee Arthroplasty Registry

Directory of Open Access Journals (Sweden)

Hamidreza Aslani

2016-04-01

Full Text Available Periodic evaluation and monitoring the health and economic outcome of joint replacement surgery is a common and popular process under the territory of joint registries in many countries. In this article we introduce the methodology used for the foundation of the National Iranian Joint Registry (IJR with a joint collaboration of the Social Security Organization (SSO and academic research departments considering the requirements of the Iran’s Ministry of Health and Education.

Government of Canada Initiatives in Support of the Joint Convention

International Nuclear Information System (INIS)

Brown, P.A.; Metcalfe, D.E.; Lojk, R.

2006-01-01

The Government of Canada strongly supported international efforts to bring into force the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention), and was the second country to ratify it. The Joint Convention places a number of obligations on Contracting Parties aimed at achieving and maintaining a high level of safety worldwide in spent fuel and radioactive waste management, ensuring that effective defenses against potential hazards are in place during all management stages, preventing accidents with radiological consequences and mitigating their consequences should they occur. In addition to establishing and maintaining a modem regulatory framework and an independent regulatory body through the 2000 Nuclear Safety and Control Act, the Government of Canada has implemented a number of initiatives that address its responsibilities and serve to further enhance Canada's compliance with the Joint Convention. For nuclear fuel waste, the Government of Canada brought into force the Nuclear Fuel Waste Act in 2002 to require waste owners to develop, fund, organize and implement a long-term solution for Canada's nuclear fuel waste. The Act clearly reserves for Government the decision on the solution to be implemented in the best interests of Canadians, as well as oversight to ensure that waste owners are fulfilling their responsibilities. In the case of low-level radioactive waste, long-term solutions are being developed to ensure the protection of health, safety, and the environment, both now and in the future. Regarding uranium mine and mill tailings, current operators have state-of-the-art waste management facilities in place. The Government of Canada works with provincial governments to ensure that any potential abandoned or legacy mines sites where no owner can be held responsible are safely decommissioned and managed over the long term. (authors)

On-line generation of three-dimensional core power distribution using incore detector signals to monitor safety limits

International Nuclear Information System (INIS)

Jang, Jin Wook; Lee, Ki Bog; Na, Man Gyun; Lee, Yoon Joon

2004-01-01

It is essential in commercial reactors that the safety limits imposed on the fuel pellets and fuel clad barriers, such as the Linear Power Density (LPD) and the Departure from Nucleate Boiling Ratio (DNBR), are not violated during reactor operations. In order to accurately monitor the safety limits of current reactor states, a detailed three-dimensional (3D) core power distribution should be estimated from the in-core detector signals. In this paper, we propose a calculation methodology for detailed 3D core power distribution, using in-core detector signals and core monitoring constants such as the 3D Coupling Coefficients (3DCC), node power fraction, and pin-to-node factors. Also, the calculation method for several core safety parameters is introduced. The core monitoring constants for the real core state are promptly provided by the core design code and on-line MASTER(Multi-purpose Analyzer for Static and Transient Effects of Reactors), coupled with the core monitoring program. Through the plant computer, core state variables, which include reactor thermal power, control rod bank position, boron concentration, inlet moderator temperature, and flow rate, are supplied as input data for MASTER. MASTER performs the core calculation based on the neutron balance equation and generates several core monitoring constants corresponding to the real core state in addition to the expected core power distribution. The accuracy of the developed method is verified through a comparison with the current CECOR method. Because in all the verification calculation cases the proposed method shows a more conservative value than the best estimated value and a less conservative one than the current CECOR and COLSS methods, it is also confirmed that this method secures a greater operating margin through the simulation of the YGN-3 cycle-1 core from the viewpoint of the power peaking factor for the LPD and the pseudo hot pin axial power distribution for the DNBR calculation

Regulatory control of radiation sources. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The basic requirements for the protection of persons against exposure to ionizing radiation and for the safety of radiation sources were established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards), jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (OECD/ NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO) (the Sponsoring Organizations). The application of the Basic Safety Standards is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities for radiation protection and safety. Requirements relating to the legal and governmental infrastructure for the safety of nuclear facilities and sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material are established in the Safety Requirements on Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety Standards Series No. GS-R-1. This Safety Guide, which is jointly sponsored by the FAO, the IAEA, the International Labour Office, the PAHO and the WHO, gives detailed guidance on the key elements for the organization and operation of a national regulatory infrastructure for radiation safety, with particular reference to the functions of the national regulatory body that are necessary to ensure the implementation of the Basic Safety Standards. The Safety Guide is based technically on material first published in IAEA-TECDOC-10671, which was jointly sponsored by the FAO, the IAEA, the OECD/NEA, the PAHO and the WHO. The requirements established in GS-R-1 have been taken into account. The Safety Guide is oriented towards national

Modelling and Experimental Testing of Hybrid Joints Made of: Aluminium Adherends, Adhesive Layers and Rivets for Aerospace Applications

Directory of Open Access Journals (Sweden)

Sadowski T.

2017-09-01

Full Text Available The contemporary demands in different branches of engineering require application of new multi-component materials and structural systems. Appropriately chosen joining technology can offer significant enhancement of structural system performance in terms of effectiveness, reliability, safety and other design criteria. The modern applications of complex joints are of great technological interest as they permit to combine and to enhance the individual effects of each kind of joint. This is of great importance for modern applications in different branches of engineering: aerospace, mechanical and civil. Therefore in this paper we will focus on the analysis of mechanical response of adhesive joint of aluminium strips reinforced by rivets. The aim of the paper is to investigate experimentally the mechanical behaviour of adhesive joint of aluminium strips reinforced by rivets for industrial applications in aerospace. The considered joint was subjected to uniaxial loading. The tests in this paper were performed for: • classical adhesive joint in order to investigate material parameters for numerical modelling of the hybrid joint • hybrid joining of the structural elements in order to investigate the reinforcement effect. The experiments with application of digital image ARAMIS system allowed for on-line monitoring of the deformation process of the considered joining elements. The particular distributions of displacement fields at the joint surface were estimated for any stage of loading process. Numerical modelling was performed for experimentally investigated specimens. The materials parameters, necessary for calculation, were estimated from experiments. FEA modelling was done with the help of ABAQUS code.

Examination of issues related to the development and implementation of real-time operational safety monitoring tools in the nuclear power industry

International Nuclear Information System (INIS)

Puglia, William J.; Atefi, Bahman

1995-01-01

In recent years, risk and reliability techniques have been increasingly used to optimize deterministic requirements and to improve the operational safety of nuclear power stations. This paper discusses the historical development and current status of implementation of real-time operational safety monitoring tools in the nuclear power industry worldwide. A safety monitor is defined as a PC-based risk management tool, based on a plant specific PSA, which can be used to manage plant safety during the day-to-day operation of a nuclear power plant by planning maintenance activities and providing advisory information to plant operational staff in order to avoid high risk plant configurations. As this technique has only been applied in a few plants worldwide, the technology is still evolving and there are several technical and implementation-related issues which still need to be resolved. This paper attempts to summarize all such issues and describe how they have been addressed in several different applications of this technology around the world

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

International Nuclear Information System (INIS)

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

2000-01-01

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

The use of embedded sensors for the monitoring of adhesive joints in marine environments

Science.gov (United States)

McGovern, Scott T.; Spinks, Geoffrey M.; Wallace, Gordon G.

2005-05-01

A copolymer incorporating polyaniline was used as a sensing medium in the construction of a resistance based humidity sensor. Aniline monomer was polymerised in the presence of poly (butyl acrylate / vinyl acetate) and a copolymer containing polyaniline emeraldine salt was obtained. The sensing medium was then developed by redissolving 1-2 w/w% of the resulting polymer residue in dichloromethane to produce a processable polymer blend solution. Some of this polymer residue was also de-doped in a solution of ammonia, and then washed with distilled water until the waste water had a neutral pH. This residue was then redissolved at 1-2 w/w% in dichloromethane to produce a second processable polymer blend this time containing polyaniline emeraldine base. The final sensor design utilised 125μm polyester insulated platinum wire as conducting electrodes that were dip coated in the emeraldine salt copolymer solution and allowed to dry in a desiccator. The sensor was then dip-coated in a protective barrier layer of the emeraldine base copolymer to prevent over-oxidation and/or de-protonation of the emeraldine salt sensing medium under this coating. The sensors had an overall final thickness of less than 150μm and showed high sensitivity to humidity, low resistance, and good reversibility without hysteresis. Sensors were monitored for 2-probe resistance changes when in contact with water. Calibration curves for each sensor were produced to convert the resistance reading to mass uptake of water. Individual sensors were embedded within Aluminium 5083 / Araldite 2015 adhesive joints to monitor mass uptake of water when exposed to marine environments. Correlations between mass uptake of water and joint strength were made. There are various advantages of such a sensor design. Polymer based thin film humidity sensors have the advantage that the high processability of the material allows for simple fabrication of a range of geometries including smaller sensor designs. The ease of

Optimization and Characterization of the Friction Stir Welded Sheets of AA 5754-H111: Monitoring of the Quality of Joints with Thermographic Techniques

Directory of Open Access Journals (Sweden)

Luigi Alberto Ciro De Filippis

2017-10-01

Full Text Available Friction Stir Welding (FSW is a solid-state welding process, based on frictional and stirring phenomena, that offers many advantages with respect to the traditional welding methods. However, several parameters can affect the quality of the produced joints. In this work, an experimental approach has been used for studying and optimizing the FSW process, applied on 5754-H111 aluminum plates. In particular, the thermal behavior of the material during the process has been investigated and two thermal indexes, the maximum temperature and the heating rate of the material, correlated to the frictional power input, were investigated for different process parameters (the travel and rotation tool speeds configurations. Moreover, other techniques (micrographs, macrographs and destructive tensile tests were carried out for supporting in a quantitative way the analysis of the quality of welded joints. The potential of thermographic technique has been demonstrated both for monitoring the FSW process and for predicting the quality of joints in terms of tensile strength.

Optimization and Characterization of the Friction Stir Welded Sheets of AA 5754-H111: Monitoring of the Quality of Joints with Thermographic Techniques.

Science.gov (United States)

De Filippis, Luigi Alberto Ciro; Serio, Livia Maria; Palumbo, Davide; De Finis, Rosa; Galietti, Umberto

2017-10-11

Friction Stir Welding (FSW) is a solid-state welding process, based on frictional and stirring phenomena, that offers many advantages with respect to the traditional welding methods. However, several parameters can affect the quality of the produced joints. In this work, an experimental approach has been used for studying and optimizing the FSW process, applied on 5754-H111 aluminum plates. In particular, the thermal behavior of the material during the process has been investigated and two thermal indexes, the maximum temperature and the heating rate of the material, correlated to the frictional power input, were investigated for different process parameters (the travel and rotation tool speeds) configurations. Moreover, other techniques (micrographs, macrographs and destructive tensile tests) were carried out for supporting in a quantitative way the analysis of the quality of welded joints. The potential of thermographic technique has been demonstrated both for monitoring the FSW process and for predicting the quality of joints in terms of tensile strength.

Development of FBR piping bellows joint

International Nuclear Information System (INIS)

Tsukimori, Kazuyuki; Iwata, Koji

1991-01-01

Reduction of construction cost is one of the most important problems to realize a FBR (Fast Breeder Reactor) Plant. Significant reduction of the construction cost of a reactor building, related equipments and facilities can be expected by shortening the length of its long cooling pipes. Since the bellows has a great capacity for absorbing thermal expansion displacement, application of bellows expansion joints is considered as the most influential measure for reduction of the piping length. To confirm technological possibilities of application and practical use of bellows joints in the main piping systems, extensive R and D's, development of various methods for evaluating the strength of bellows, establishment of inspection and maintenance techniques, studies on safety logic, etc., were carried out by PNC from 1983 to 1988. Through these studies, technological possibilities of bellows joints were confirmed and the results were summarized in the 'Structural Design Guide for Class 1 Piping Bellows Expansion Joints of Fast Breeder Reactor for Elevated Temperature Service' and the 'Inspection and Maintenance Standards of Piping bellows expansion Joints'. (author)

49 CFR 571.221 - Standard No. 221, School bus body joint strength.

Science.gov (United States)

2010-10-01

... 49 Transportation 6 2010-10-01 2010-10-01 false Standard No. 221, School bus body joint strength. 571.221 Section 571.221 Transportation Other Regulations Relating to Transportation (Continued) NATIONAL HIGHWAY TRAFFIC SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR VEHICLE SAFETY STANDARDS Federal Motor Vehicle Safety Standard...

An American knowledge base in England - Alternate implementations of an expert system flight status monitor

Science.gov (United States)

Butler, G. F.; Graves, A. T.; Disbrow, J. D.; Duke, E. L.

1989-01-01

A joint activity between the Dryden Flight Research Facility of the NASA Ames Research Center (Ames-Dryden) and the Royal Aerospace Establishment (RAE) on knowledge-based systems has been agreed. Under the agreement, a flight status monitor knowledge base developed at Ames-Dryden has been implemented using the real-time AI (artificial intelligence) toolkit MUSE, which was developed in the UK. Here, the background to the cooperation is described and the details of the flight status monitor and a prototype MUSE implementation are presented. It is noted that the capabilities of the expert-system flight status monitor to monitor data downlinked from the flight test aircraft and to generate information on the state and health of the system for the test engineers provides increased safety during flight testing of new systems. Furthermore, the expert-system flight status monitor provides the systems engineers with ready access to the large amount of information required to describe a complex aircraft system.

Design and research of safety monitor and control system based on CAN BUS

International Nuclear Information System (INIS)

Wen Xinling; Chen Yu; Zhang Zhen; Zhao Yubin

2007-01-01

In Order to protect machine operator under danger work area in producing-manufacturing industry, we present a distributed safety monitor and control system based on CAN BUS technology. The detection signal is collected based on the photo-voltage characteristics of the infrared sensor and it was processed with the core of AT89C51. The microprocessor controls the CAN BUS controller SJA1000/transceiver PCA82C250 to structure CAN BUS communication system to transmit the data. Through the serial interface MAX232 connected main controller with each control node, PC can monitor and control each machine in real time and renew control scheme. This paper introduces composition principle and the methods of hardware design in detail. Experiments shown that the system has yield control precision of 0.1 mm, defend distance more than 15 m and the measurement accuracy of 100%. Moreover, it can realize to reform FA431 and monitor cotton-breaking, yarn-breaking and product quality. Productivity is improved about 25%-35%. (authors)

CloudSat Safety Operations at Vandenberg AFB

Science.gov (United States)

Greenberg, Steve

2006-01-01

CloudSat safety operations at Vendenberg AFB is given. The topics include: 1) CloudSat Project Overview; 2) Vandenberg Ground Operations; 3) Delta II Launch Vehicle; 4) The A-Train; 5) System Safety Management; 6) CALIPSO Hazards Assessment; 7) CALIPSO Supplemental Safeguards; 8) Joint System Safety Operations; 9) Extended Stand-down; 10) Launch Delay Safety Concerns; and 11) Lessons Learned.

Safety analysis report: A comparison of incidents from Safety Years 2006 through 2010, USDA Forest Service, Rocky Mountain Research Station Inventory and Monitoring Program

Science.gov (United States)

Devon Donahue

2012-01-01

This paper is an analysis of 5 years of accident data for the USDA Forest Service, Rocky Mountain Research Station (RMRS) Inventory and Monitoring (IM) Program that identifies past trends, allows for standardized self-comparison, and increases our understanding of the true costs of injuries and accidents. Measuring safety is a difficult task. While most agree that...

Configuration of Risk Monitor System by PLant Defense-In.Depth Monitor and Relability Monitor

DEFF Research Database (Denmark)

Yoshikawa, Hidekazu; Lind, Morten; Yang, Ming

2012-01-01

A new method of risk monitor system of a nuclear power plant has been proposed from the aspect by what degree of safety functions incorporated in the plant system is maintained by multiple barriers of defense-in-depth (DiD). Wherein, the central idea is plant DiD risk monitor and reliability...... monitor derived from the four aspects of (i) design principle of nuclear safety to realize DiD concept, (ii) definition of risk and risk to be monitored, (iii) severe accident phenomena as major risk, (iv) scheme of risk ranking, and (v) dynamic risk display. In this paper, the overall frame...... of the proposed frame on risk monitor system is summarized and the detailed discussion is made on the definitions of major terminologies of risk, risk ranking, anatomy of fault occurrence, two-layer configuration of risk monitor, how to configure individual elements of plant DiD risk monitor and its example...

Rule-based Dynamic Safety Monitoring for Mobile Robots

DEFF Research Database (Denmark)

Adam, Marian Sorin; Larsen, Morten; Jensen, Kjeld

2016-01-01

—Safety is a key challenge in robotics, in particular for mobile robots operating in an open and unpredictable environment. Safety certification is desired for commercial robots, but no existing approaches for addressing the safety challenge provide a clearly specified and isolated safety layer......, defined in an easily understandable way for facilitating safety certification. In this paper, we propose that functional-safety-critical concerns regarding the robot software be explicitly declared separately from the main program, in terms of externally observable properties of the software. Concretely...

Road Safety Data, Collection, Transfer and Analysis DaCoTa. Workpackage 6, Driver Behaviour Monitoring through Naturalistic Driving: Deliverable 6.3: Report on small scale naturalistic driving pilot.

NARCIS (Netherlands)

Pilgerstorfer, M. Runda, K. Brandstätter, C. Christoph, M. Hakkert, S. Ishaq, R. Toledo, T. & Gatscha, M.

2012-01-01

WP6 of DaCoTA, Driver Behaviour Monitoring through Naturalistic Driving, aims to develop an implementation plan for a large scale activity that uses Naturalistic Driving (ND) Observations to continuously monitor relevant road safety data within the framework of the European Road Safety Observatory.

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in … shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

The safety monitor and RCM workstation as complementary tools in risk based maintenance optimization

International Nuclear Information System (INIS)

Rawson, P.D.

2000-01-01

Reliability Centred Maintenance (RCM) represents a proven technique for rendering maintenance activities safer, more effective, and less expensive, in terms of systems unavailability and resource management. However, it is believed that RCM can be enhanced by the additional consideration of operational plant risk. This paper discusses how two computer-based tools, i.e., the RCM Workstation and the Safety Monitor, can complement each other in helping to create a living preventive maintenance strategy. (author)

Utilizing data consortia to monitor safety and effectiveness of biosimilars and their innovator products.

Science.gov (United States)

Baldziki, Mike; Brown, Jeff; Chan, Hungching; Cheetham, T Craig; Conn, Thomas; Daniel, Gregory W; Hendrickson, Mark; Hilbrich, Lutz; Johnson, Ayanna; Miller, Steven B; Moore, Tom; Motheral, Brenda; Priddy, Sarah A; Raebel, Marsha A; Randhawa, Gurvaneet; Surratt, Penny; Walraven, Cheryl; White, T Jeff; Bruns, Kevin; Carden, Mary Jo; Dragovich, Charlie; Eichelberger, Bernadette; Rosato, Edith; Sega, Todd

2015-01-01

The Biologics Price Competition and Innovation Act, introduced as part of the Affordable Care Act, directed the FDA to create an approval pathway for biologic products shown to be biosimilar or interchangeable with an FDA-approved innovator drug. These biosimilars will not be chemically identical to the reference agent. Investigational studies conducted with biosimilar agents will likely provide limited real-world evidence of their effectiveness and safety. How do we best monitor effectiveness and safety of biosimilar products once approved by the FDA and used more extensively by patients? To determine the feasibility of developing a distributed research network that will use health insurance plan and health delivery system data to detect biosimilar safety and effectiveness signals early and be able to answer important managed care pharmacy questions from both the government and managed care organizations. Twenty-one members of the AMCP Task Force on Biosimilar Collective Intelligence Systems met November 12, 2013, to discuss issues involved in designing this consortium and to explore next steps. The task force concluded that a managed care biosimilars research consortium would be of significant value. Task force members agreed that it is best to use a distributed research network structurally similar to existing DARTNet, HMO Research Network, and Mini-Sentinel consortia. However, for some surveillance projects that it undertakes, the task force recognizes it may need supplemental data from managed care and other sources (i.e., a "hybrid" structure model). The task force believes that AMCP is well positioned to lead the biosimilar-monitoring effort and that the next step to developing a biosimilar-innovator collective intelligence system is to convene an advisory council to address organizational governance.

Ninth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Raeder, J.; Gordon, C.

2001-01-01

The ninth ITER Technical Meeting on safety and environment, the last in the course of the ITER Engineering Design Activities (EDA), was held at the ITER Garching Joint Work site, 8 to 10 May 2001. At this Meeting, safety experts from the House Teams worked together with the members of the Safety, Environment and Health Groups (SEHG) of the ITER Joint Central Team (JCT) in the following areas: finalization of the Generic Site Safety report (GSSR) which is considered to be the most important objective of the present work; summary of the safety related R and D work done by the Home Teams for ITER during EDA; review of verification and validation work done on computer codes being applied for Safety and Environment (S and E) analyses; outline of work considered necessary for improving the S and E database, quantifying uncertainties of the code results and preparing the adaptation of ITER to a specific site

Sixth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Saji, G.; Baker, D.

1997-01-01

The article summarizes the topics of the Sixth Technical Meeting on Safety and Environment which was held to review the first draft of the Non-Site Specific Safety Report (NSSR-2) and the draft of the ITER Final Design Report Safety Assessment (FDR-Safety) during October 27 - November 4, 1997 at the ITER San Diego Joint Work Site

Finnish remote environmental monitoring field demonstration

International Nuclear Information System (INIS)

Toivonen, H.; Leppaenen, A.; Ylaetalo, S.; Lehtinen, J.; Hokkinen, J.; Tarvainen, M.; Crawford, T.; Glidewell, D.; Smartt, H.; Torres, J.

1997-10-01

Radiation and Nuclear Safety Authority (STUK), Helsinki, Finland and Sandia National Laboratories (SNL), working under the Finnish Support Program to IAEA Safeguards and the United States Department of Energy (DOE) funded International Remote Monitoring Program (Task FIN E 935), have undertaken a joint effort to demonstrate the use of remote monitoring for environmental air sampling and safeguards applications. The results of the task will be used by the IAEA to identify the feasibility, cost-effectiveness, reliability, advantages, and problems associated with remote environmental monitoring. An essential prerequisite for a reliable remote air sampling system is the protection of samples against tampering. Means must be developed to guarantee that the sampling itself has been performed as designed and the original samples are not substituted with samples produced with other equipment at another site. One such method is to label the samples with an unequivocal tag. In addition, the inspection personnel must have the capability to remotely monitor and access the automated environmental air sampling system through the use of various sensors and video imagery equipment. A unique aspect to this project is the network integration of remote monitoring equipment with a STUK radiation monitoring system. This integration will allow inspectors to remotely view air sampler radiation data and sensor/image data through separate software applications on the same review station. A sensor network and video system will be integrated with the SNL developed Modular Integrated Monitoring System (MIMS) to provide a comprehensive remote monitoring approach for safeguards purposes. This field trial system is being implemented through a multiphase approach for use by STUK, SNL, and for possible future use by the IAEA

The Nordic Nuclear Safety Research (NKS) programme. Nordic cooperation on nuclear safety

Energy Technology Data Exchange (ETDEWEB)

Andersson, Kasper G. [Technical Univ. of Denmark, Roskilde (Denmark). National Lab. for Sustainable Energy; Ekstroem, Karoliina [Fortum Power and Heat, Fortum (Finland); Gwynn, Justin P. [Norwegian Radiation Protection Authority, Tromsoe (Norway). Fram Centre; Magnusson, Sigurdur M. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Physant, Finn C. [NKS-Sekretariatet, Roskilde (Denmark)

2012-07-01

The roots of the current Nordic Nuclear Safety Research (NKS) programme can be traced back to the recommendation by the Nordic Council in the late 1950s for the establishment of joint Nordic committees on the issues of nuclear research and radiation protection. One of these joint Nordic committees, the 'Kontaktorgan', paved the way over its 33 years of existence for the future of Nordic cooperation in the field of nuclear safety, through the formation of Nordic groups on reactor safety, nuclear waste and environmental effects of nuclear power in the late 1960s and early 1970s. With an increased focus on developing nuclear power in the wake of the energy crisis on the 1970s, the NKS was established by the Nordic Council to further develop the previous strands of Nordic cooperation in nuclear safety. NKS started its first programme in 1977, funding a series of four year programmes over the next 24 years covering the areas of reactor safety, waste management, emergency preparedness and radioecology. Initially funded directly from the Nordic Council, ownership of NKS was transferred from the political level to the national competent authorities at the beginning of the 1990s. This organizational and funding model has continued to the present day with additional financial support from a number of co-sponsors in Finland, Norway and Sweden. (orig.)

Road Safety Data, Collection, Transfer and Analysis DaCoTa. Workpackage 6, Driver Behaviour Monitoring through Naturalistic Driving: Deliverable 6.5: Naturalistic Driving for cross-national monitoring of SPIs and Exposure : an overview.

NARCIS (Netherlands)

Wegman, R.W.N. & Bos, N.M.

2015-01-01

WP6 of DaCoTA, Driver Behaviour Monitoring through Naturalistic Driving, focuses on the usefulness and feasibility of applying the Naturalistic Driving method for monitoring within the framework of ERSO. The aim is to continuously collect comparable information about the road safety level in EU

Cryotherapy impairs knee joint position sense.

Science.gov (United States)

Oliveira, R; Ribeiro, F; Oliveira, J

2010-03-01

The effects of cryotherapy on joint position sense are not clearly established; however it is paramount to understand its impact on peripheral feedback to ascertain the safety of using ice therapy before resuming exercise on sports or rehabilitation settings. Thus, the aim of the present study was to determine the effects of cryotherapy, when applied over the quadriceps and over the knee joint, on knee position sense. This within-subjects repeated-measures study encompassed fifteen subjects. Knee position sense was measured by open kinetic chain technique and active positioning at baseline and after cryotherapy application. Knee angles were determined by computer analysis of the videotape images. Twenty-minute ice bag application was applied randomly, in two sessions 48 h apart, over the quadriceps and the knee joint. The main effect for cryotherapy application was significant (F (1.14)=7.7, p=0.015) indicating an increase in both absolute and relative angular errors after the application. There was no significant main effect for the location of cryotherapy application, indicating no differences between the application over the quadriceps and the knee joint. In conclusion, cryotherapy impairs knee joint position sense in normal knees. This deleterious effect is similar when cryotherapy is applied over the quadriceps or the knee joint. Georg Thieme Verlag KG Stuttgart.New York.

Behavior of single lap composite bolted joint under traction loading: Experimental investigation

Science.gov (United States)

Awadhani, L. V.; Bewoor, Anand

2018-04-01

Composite bolted joints are preferred connection in the composite structures to facilitate the dismantling for the replacements/ maintenance work. The joint behavior under tractive forces has been studied in order to understand the safety of the structure designed. The main objective of this paper is to investigate the behavior of single-lap joints in carbon fiber reinforced epoxy composites under traction loading conditions. The experiments were designed to identify the effect of bolt diameter, stacking sequence and loading rate on the properties of the joint. The experimental results show that the parameters influence the joint performance significantly.

STUDY, EVALUATION AND TEST OF SUBMODULE TO GIRDER BOLTED JOINT

CERN Document Server

Blocki, J; Miralles, Ll; Topilin, N D

2000-01-01

The object of the present work is to study the bolted joint submodule to girder. This joint is critical from the point of view of the mechanical integrity of the Tilecal Barrel and Extended Barrel modules and LAr Endcaps. Theoretical analysis, FEM calculations and tests have been carried out in order to find a solution that fulfils the safety factors design criteria.

MR-guided facet joint injection therapy using an open 1.0-T MRI system: an outcome study

International Nuclear Information System (INIS)

Freyhardt, Patrick; Bucourt, Maximilian de; Maurer, Martin; Renz, Diane; Gebauer, Bernhard; Hamm, Bernd; Streitparth, Florian; Hartwig, Tony; Teichgraeber, Ulf K.M.

2013-01-01

To evaluate the accuracy, safety and efficacy of magnetic resonance imaging (MRI)-guided facet joint injection therapy using a 1.0-T open MRI. One hundred and sixty-six facet joint blocks in 45 patients with lower back pain were performed under MR fluoroscopic guidance using a proton-density-weighted turbo-spin-echo sequence. An in-room monitor, wireless MR-mouse for operator-controlled multiplanar navigation, a flexible surface coil and MR-compatible 20-G needle were used. Clinical outcome was evaluated by questionnaire before intervention and after 1 week, 3, 6 and 12 months using a numerical visual analogue scale (VAS). All facet joint blocks were considered technically successful with distribution of the injectant within and/or around the targeted facet joint. No major complications occurred. The final outcome analysis included 38 patients. An immediate effect was reported by 63 % of the patients. A positive mid-/long-term effect was seen in 13 patients (34 %) after 6 months and in 9 patients (24 %) after 12 months. Mean VAS was reduced from 7.1 ± 1.7 (baseline) to 3.5 ± 2.2, 4.1 ± 3.0, 3.8 ± 2.9 and 4.6 ± 2.9 at 1 week, 3, 6 and 12 months (P < 0.01). MR-guided facet joint injection therapy of the lumbosacral spine is accurate, safe and efficient in the symptomatic treatment of lower back pain. (orig.)

Safety evaluation methodology of engineering barriers at repository for low and intermediate level radioactive waste

International Nuclear Information System (INIS)

Zarnic, R.; Bokan Bosiljkov, V.; Giacomelli, M.

2007-01-01

Analyses of the roles of cement-based barriers in radioactive waste isolation show that models used to estimate their characteristics during the lifetime of the repository must consider the alteration of material properties with time due to degradation processes. Reinforced concrete barriers at repositories shall be designed in such manner that they fulfil besides isolative capabilities also the required functions of mechanical resistance and stability. Key elements of safety evaluation are mainly the correct selection of materials for mineral composites with cement binder (cements, aggregates, mineral additives and chemical admixtures) and their design, execution of construction works and production of precast concrete containers (continuous casting of concrete - no cold joints, limited number of construction joints, proper placing and consolidation, finishing and curing), strict control of used materials and inspection of works, as well as investigation after the construction (visual inspection, non-destructive testing, monitoring, ageing assessment on test containers). According to the methodology presented in this paper the lifetime of the repository can be estimated and, if shorter than 300 years or shorter than the period resulting from safety analysis, appropriate corrective measures shall be taken. (author)

Short presentation of the activities of the Joint Research Center, Ispra establishment in the field of material research in reactor safety

Energy Technology Data Exchange (ETDEWEB)

Larsson, H [JRC, Ispra (Italy)

1977-07-01

The Commission of the European Communities (CEC) disposes of a joint Research Center (JRC) composed of four establishments. In the ISPRA establishment, which is the largest of four, the largest project, Reactor Safety, includes the following: reliability analysis; blowdown; sodium thermohydraulics; fuel-coolant interaction and post accident heat removal; dynamic structural loading and response (LMFBR); structural failure prevention. The last is described in this paper. It deals with: code validation program for primary containment response in a LMFBR following core disruptive accident (COVA); dynamic material testing; fracture mechanics; creep fatigue; creep crack growth; creep damage evaluation; non-destructive testing.

Undersafe: Monitoring safety parameters in touristic mines and caves

Science.gov (United States)

Parcerisa, David; Sanmiquel, Lluís; Alfonso, Pura; Oliva, Josep

2014-05-01

Tourism is a key sector of the European economy, generating more than 5% of the EU GPD (Gross Domestic Product). Usually, underground touristic sites receive non-expert visitors; nevertheless these activities are poorly regulated or completely deregulated. Nowadays, safety is provided by underground expert professionals whom proceed to regular inspections and by basic safety infrastructures. Even with these measures, some potential personal and environmental dangers are always present and cannot be totally avoided. Therefore, there is a clear need of a new technological product for safety and environmental continuous monitoring of tourist underground attractions. So, the aim of the Undersafe project is to provide underground attractions with a novel and specifically tailored monitoring system, easy to use and maintain. One of the goals of the Undersafe project is to develop a rock falling detection based on a set of cost limited vibration sensors. Based on the technical needs, but with cost constraints, different types of potential sensors are considered: Underground microphone: It is placed in the surface or in the underground. It is based on the consideration that the impact of the stone generates a ground impact vibration which can be understood as a "noise" that is received by a microphone capsule. Airborne sound sensing microphone: It similarly applies to underground use of the microphones, but now the microphone is tested as for its traditional use (I.e. air sound detection). In such case, the microphone detects the environmental noise produced by the impact of the stone falling onto the ground, which will include the impact sound of the stone. Geophone: It is the de facto standard for ground vibrations. Although this technology was initially discarded due to its high cost, recently, low cost geophones have appeared in the market that allows its use inside the underground attractions. Accelerometers: These, can have enough sensibility to act as vibration

Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Report of the Federal Republic of Germany for the sixth review meeting in May 2018; Gemeinsames Uebereinkommen ueber die Sicherheit der Behandlung abgebrannter Brennelemente und ueber die Sicherheit der Behandlung radioaktiver Abfaelle. Bericht der Bundesrepublik Deutschland fuer die sechste Ueberpruefungskonferenz im Mai 2018

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-08-15

The joint convention on the safety of spent fuel management and on the safety of radioactive waste management covers the following topics: historical development and actual status of the civil use of nuclear power, politics and the spent fuel management, inventories and listing, legislation and executive systems, other safeguard regulations, safety during spent fuel handling, safety during radioactive waste processing, transport across national borders, disused enclosed radioactive sources, general regulations for safety enhancement.

Self-, other-, and joint monitoring using forward models

Directory of Open Access Journals (Sweden)

Martin John Pickering

2014-03-01

Full Text Available In the psychology of language, most accounts of self-monitoring assume that it is based on comprehension. Here we outline and develop the alternative account proposed by Pickering and Garrod (2013, in which speakers construct forward models of their upcoming utterances and compare them with the utterance as they produce them. We propose that speakers compute inverse models derived from the discrepancy (error between the utterance and the predicted utterance and use that to modify their production command or (occasionally begin anew. We then propose that comprehenders monitor other people’s speech by simulating their utterances using covert imitation and forward models, and then comparing those forward models with what they hear. They use the discrepancy to compute inverse models and modify their representation of the speaker’s production command, or realize that their representation is incorrect and may develop a new production command. We then discuss monitoring in dialogue, paying attention to sequential contributions, concurrent feedback, and the relationship between monitoring and alignment.

Magnetic resonance imaging of hip joint cartilage and labrum

Directory of Open Access Journals (Sweden)

Christoph Zilkens

2011-09-01

Full Text Available Hip joint instability and impingement are the most common biomechanical risk factors that put the hip joint at risk to develop premature osteoarthritis. Several surgical procedures like periacetabular osteotomy for hip dysplasia or hip arthroscopy or safe surgical hip dislocation for femoroacetabular impingement aim at restoring the hip anatomy. However, the success of joint preserving surgical procedures is limited by the amount of pre-existing cartilage damage. Biochemically sensitive MRI techniques like delayed Gadolinium Enhanced MRI of Cartilage (dGEMRIC might help to monitor the effect of surgical or non-surgical procedures in the effort to halt or even reverse joint damage.

Respiratory pattern changes during costovertebral joint movement.

Science.gov (United States)

Shannon, R

1980-05-01

Experiments were conducted to determine if costovertebral joint manipulation (CVJM) could influence the respiratory pattern. Phrenic efferent activity (PA) was monitored in dogs that were anesthetized with Dial-urethane, vagotomized, paralyzed, and artificially ventilated. Ribs 6-10 (bilaterally) were cut and separated from ribs 5-11. Branches of thoracic nerves 5-11 were cut, leaving only the joint nerve supply intact. Manual joint movement in an inspiratory or expiratory direction had an inhibitory effect on PA. Sustained displacement of the ribs could inhibit PA for a duration equal to numerous respiratory cycles. CVJM in synchrony with PA resulted in an increased respiratory rate. The inspiratory inhibitory effect of joint receptor stimulation was elicited with manual chest compression in vagotomized spontaneously breathing dogs, but not with artificial lung inflation or deflation. It is concluded that the effect of CVJM on the respiratory pattern is due to stimulation of joint mechanoreceptors, and that they exert their influence in part via the medullary-pontine rhythm generator.

Radiological safety system based on real-time tritium-in-air monitoring indoor and in effluents

International Nuclear Information System (INIS)

Bidica, Nicolae; Sofalca, Nicolae; Balteanu, Ovidiu-Ioan; Stefan, Ioana-Iuliana

2007-01-01

In this paper we describe an improved real-time tritium monitoring system designed for Heavy Water Detritiation Pilot Plant of National Institute for Cryogenics and Isotopes Separation, Rm. Valcea, Romania. The system consists of three fixed tritium-in-air monitors which measure continuously tritium-in-air concentration (in both species: vapour and gas) in working areas and gaseous effluents. Portable tritium monitors with ionization chamber, and tritium-in-air collector combined with liquid scintillation counter method are also used to supplement fixed instrument measurements. The main functions of tritium monitoring system are: to measure tritium-in air concentration in working areas and gaseous effluents; to alarm the personnel if tritium concentration thresholds are exceeded; to integrate tritium activity released to the environment during a week and to cut off normal ventilation when the activity threshold is exceeded and start the air cleaning system. Now, several especial functions have been added, so that by using appropriate conversion factors, the tritium monitoring system is able to estimate the effective dose rate before starting an activity into the monitored area, during this activity, or soon as the activity was finished. Another new function has been added by coupling tritium-in-air monitoring system with control access system. This is very useful for quick estimation of tritium doses. For routine dosimetric survey, one the internal dose for individuals by measuring tritium in urine is estimated. With all these features our tritium monitoring system is really a safety system for personnel and for environment. (authors)

Flu Vaccine Safety Information

Science.gov (United States)

... Influenza Types Seasonal Avian Swine Variant Pandemic Other Flu Vaccine Safety Information Questions & Answers Language: English (US) ... safety of flu vaccines monitored? Egg Allergy Are flu vaccines safe? Flu vaccines have good safety record. ...

In Situ Monitoring of Pb2+ Leaching from the Galvanic Joint Surface in a Prepared Chlorinated Drinking Water.

Science.gov (United States)

Ma, Xiangmeng; Armas, Stephanie M; Soliman, Mikhael; Lytle, Darren A; Chumbimuni-Torres, Karin; Tetard, Laurene; Lee, Woo Hyoung

2018-02-20

A novel method using a micro-ion-selective electrode (micro-ISE) technique was developed for in situ lead monitoring at the water-metal interface of a brass-leaded solder galvanic joint in a prepared chlorinated drinking water environment. The developed lead micro-ISE (100 μm tip diameter) showed excellent performance toward soluble lead (Pb 2+ ) with sensitivity of 22.2 ± 0.5 mV decade -1 and limit of detection (LOD) of 1.22 × 10 -6 M (0.25 mg L -1 ). The response time was less than 10 s with a working pH range of 2.0-7.0. Using the lead micro-ISE, lead concentration microprofiles were measured from the bulk to the metal surface (within 50 μm) over time. Combined with two-dimensional (2D) pH mapping, this work clearly demonstrated that Pb 2+ ions build-up across the lead anode surface was substantial, nonuniform, and dependent on local surface pH. A large pH gradient (ΔpH = 6.0) developed across the brass and leaded-tin solder joint coupon. Local pH decreases were observed above the leaded solder to a pH as low as 4.0, indicating it was anodic relative to the brass. The low pH above the leaded solder supported elevated lead levels where even small local pH differences of 0.6 units (ΔpH = 0.6) resulted in about four times higher surface lead concentrations (42.9 vs 11.6 mg L -1 ) and 5 times higher fluxes (18.5 × 10 -6 vs 3.5 × 10 -6 mg cm -2 s -1 ). Continuous surface lead leaching monitoring was also conducted for 16 h.

The EOP Visualization Module Integrated into the Plasma On-Line Nuclear Power Plant Safety Monitoring and Assessment System

International Nuclear Information System (INIS)

Hornaes, Arne; Hulsund, John Einar; Vegh, Janos; Major, Csaba; Horvath, Csaba; Lipcsei, Sandor; Kapocs, Gyoergy

2001-01-01

An ambitious project to replace the unit information systems (UISs) at the Hungarian Paks nuclear power plant was started in 1998-99. The basic aim of the reconstruction project is to install a modern, distributed UIS architecture on all four Paks VVER-440 units. The new UIS includes an on-line plant safety monitoring and assessment system (PLASMA), which contains a critical safety functions monitoring module and provides extensive operator support during the execution of the new, symptom-oriented emergency operating procedures (EOPs). PLASMA includes a comprehensive EOP visualization module, based on the COPMA-III procedure-handling software developed by the Organization for Economic Cooperation and Development, Halden Reactor Project. Intranet technology is applied for the presentation of the EOPs with the use of a standard hypertext markup language (HTML) browser as a visualization tool. The basic design characteristics of the system, with a detailed description of its user interface and functions of the new EOP display module, are presented

Industrial safety and applied health physics. Annual report for 1977

International Nuclear Information System (INIS)

Auxier, J.A.; Davis, D.M.

1978-06-01

Progress is reported on the following: radiation monitoring with regard to personnel monitoring and health physics instrumentation; environs surveillance with regard to atmospheric monitoring, water monitoring, radiation background measurements, and soil and grass samples; radiation and safety surveys with regard to laboratory operations monitoring, radiation incidents, and laundry monitoring; industrial safety and special projects with regard to accident analysis, disabling injuries, and safety awards

Potential of optical spectral transmission measurements for joint inflammation measurements in rheumatoid arthritis patients

Science.gov (United States)

Meier, A. J. Louise; Rensen, Wouter H. J.; de Bokx, Pieter K.; de Nijs, Ron N. J.

2012-08-01

Frequent monitoring of rheumatoid arthritis (RA) patients enables timely treatment adjustments and improved outcomes. Currently this is not feasible due to a shortage of rheumatologists. An optical spectral transmission device is presented for objective assessment of joint inflammation in RA patients, while improving diagnostic accuracy and clinical workflow. A cross-sectional, nonrandomized observational study was performed with this device. In the study, 77 proximal interphalangeal (PIP) joints in 67 patients have been analyzed. Inflammation of these PIP joints was also assessed by a rheumatologist with a score varying from 1 (not inflamed) to 5 (severely inflamed). Out of 77 measurements, 27 were performed in moderate to strongly inflamed PIP joints. Comparison between the clinical assessment and an optical measurement showed a correlation coefficient r=0.63, p<0.001, 95% CI [0.47, 0.75], and a ROC curve (AUC=0.88) that shows a relative good specificity and sensitivity. Optical spectral transmission measurements in a single joint correlate with clinical assessment of joint inflammation, and therefore might be useful in monitoring joint inflammation in RA patients.

IAEA Mission Sees High Commitment to Safety at Ghana's Research Reactor After HEU to LEU Fuel Conversion

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts said the operator of Ghana’s research reactor has demonstrated a high commitment to safety following the conversion of the reactor core to use low enriched uranium (LEU) as fuel instead of high enriched uranium (HEU). The team also made recommendations for further safety enhancements. The Integrated Safety Assessment for Research Reactors (INSARR) team concluded a five-day mission today to assess the safety of the GHARR-1 research reactor, originally commissioned in 1994. The 30 kW reactor, operated by the Ghana Atomic Energy Commission (GAEC) at the National Nuclear Research Institute in the capital Accra, is used primarily for trace element analysis for industrial or agricultural purposes, research, education and training. In 2017, the reactor core was converted in a joint effort by Ghana, the United States and China, with assistance from the IAEA. The IAEA supported the operation to eliminate proliferation risks associated with HEU, while maintaining important scientific research. The team made recommendations for improvements to the GAEC, including: • Completing the revision of reactor safety and operating documents to reflect the results of the commissioning of the reactor after the core fuel conversion. • Enhancing the training and qualification programme for operating personnel. • Improving the capability for monitoring operational safety parameters under all conditions. • Strengthening radiation protection by establishing an effective radiation monitoring of workplace. The GAEC said it will request a follow-up INSARR mission by 2020.

Influence of joint dip angle on seismic behaviors of rock foundation

International Nuclear Information System (INIS)

Yang, Lei; Gao, Yang; Jiang, Yujing; Li, Bo; Li Shucai

2012-01-01

The seismic response of rock foundation to seismic loads is an important issue to the stability and safety of nuclear power plants. Due to the fact that the discontinuities like joints existing in the rock mass govern principally the deformation and failure behaviors of the rock mass, the influence of discontinuities on the seismic behaviors of rock mass remains as one of the fundamental problems in the safety assessment of nuclear power plants. In this study, the distinct element method (DEM) and finite element method (FEM) were adopted to investigate the seismic responses of rock foundation to a real seismic wave, taking into account the effect of joint dip angle on the deformation and dynamic behaviors of rock foundation. In the DEM simulations, the intact rock has an amplification effect on the amplitudes of seismic waves, while the joints exhibit an attenuation effect on the seismic waves. In the FEM simulations, however, the attenuation effect of joints is not obvious. The dip angle of joints has strong effects on the deformation and dynamic behaviors of rock foundation, in terms that different dip angles lead to obviously different deformation and horizontal stress in the rock foundation when subjected to seismic load. When the dip angle of joints is around 60deg, the seismic velocity, displacement and stress reach the maximums. Therefore, attentions need to be paid on this factor during the seismic design of nuclear power plants. (author)

Safety logic systems of PFBR

International Nuclear Information System (INIS)

Sambasivan, S. Ilango

2004-01-01

Full text : PFBR is provided with two independent, fast acting and diverse shutdown systems to detect any abnormalities and to initiate safety action. Each system consists of sensors, signal processing systems, logics, drive mechanisms and absorber rods. The absorber rods of the first system are Control and Safety Rods (CSR) and that of the second are called as Diverse Safety Rods (DSR). There are nine CSR and three DSR. While CSR are used for startup, control of reactor power, controlled shutdown and SCRAM, the DSR are used only for SCRAM. The respective drive mechanisms are called as CSRDM and DSRDM. Each of these two systems is capable of executing the shutdown satisfactorily with single failure criteria. Two independent safety logic systems based on diverse principles have been designed for the two shut down systems. The analog outputs of the sensors of Core Monitoring Systems comprising of reactor flux monitoring, core temperature monitoring, failed fuel detection and core flow monitoring systems are processed and converted into binary signals depending on their instantaneous values. Safety logic systems receive the binary signals from these core-monitoring systems and process them logically to protect the reactor against postulated initiating events. Neutronic and power to flow (P/Q) signals form the inputs to safety logic system-I and temperature signals are inputs to the safety logic system II. Failed fuel detection signals are processed by both the shut down systems. The two logic systems to actuate the safety rods are also based on two diverse designs and implemented with solid-state devices to meet all the requirements of safety systems. Safety logic system I that caters to neutronic and P/Q signals is designed around combinational logic and has an on-line test facility to detect struck at faults. The second logic system is based on dynamic logic and hence is inherently safe. This paper gives an overview of the two logic systems that have been

Rehabilitation after total joint replacement: a scoping study.

Science.gov (United States)

L Snell, Deborah; Hipango, Julia; Sinnott, K Anne; Dunn, Jennifer A; Rothwell, Alastair; Hsieh, C Jean; DeJong, Gerben; Hooper, Gary

2018-07-01

The evidence supporting rehabilitation after joint replacement, while vast, is of variable quality making it difficult for clinicians to apply the best evidence to their practice. We aimed to map key issues for rehabilitation following joint replacement, highlighting potential avenues for new research. We conducted a scoping study including research published between January 2013 and December 2016, evaluating effectiveness of rehabilitation following hip and knee total joint replacement. We reviewed this work in the context of outcomes described from previously published research. Thirty individual studies and seven systematic reviews were included, with most research examining the effectiveness of physiotherapy-based exercise rehabilitation after total knee replacement using randomized control trial methods. Rehabilitation after hip and knee replacement whether carried out at the clinic or monitored at home, appears beneficial but type, intensity and duration of interventions were not consistently associated with outcomes. The burden of comorbidities rather than specific rehabilitation approach may better predict rehabilitation outcome. Monitoring of recovery and therapeutic attention appear important but little is known about optimal levels and methods required to maximize outcomes. More work exploring the role of comorbidities and key components of therapeutic attention and the therapy relationship, using a wider range of study methods may help to advance the field. Implications for Rehabilitation Physiotherapy-based exercise rehabilitation after total hip replacement and total knee replacement, whether carried out at the clinic or monitored at home, appears beneficial. Type, intensity, and duration of interventions do not appear consistently associated with outcomes. Monitoring a patient's recovery appears to be an important component. The available research provides limited guidance regarding optimal levels of monitoring needed to achieve gains following hip

Fifth review meeting of the contracting parties of the joint convention

International Nuclear Information System (INIS)

Brennecke, Peter

2015-01-01

The 5 th Review Meeting of the ''Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management'' was held at International Atomic Energy Agency (IAEA) Headquarters in Vienna on 11 to 22 May 2015. Sixty-one of sixty-nine Contracting Parties with more than 700 delegates and the OECD/NEA as an observer attended the meeting. Within this regularly scheduled meeting every three years it is checked in which way the contracting parties meet the objectives of the Joint Convention, i.e., the respective national radioactive waste management policy and its implementation is critically reviewed, the respective reached safety level discussed and - where necessary - improvements suggested. As a result the Contracting Parties in particular concur that the 5 th Review Meeting encouraged constructive exchanges and sharing of knowledge. Some highlights of good progress and significant accomplishments since the 4 th Review Meeting include, e.g., the implementation of national policies, strategies and programs for spent fuel and radioactive waste management or the construction and commissioning of storage facilities and repositories for spent fuel and radioactive waste. The 6 th Review Meeting of the Contracting Parties to the Joint Convention will be held at IAEA Headquarters in Vienna on 21 May to 1 June 2018.

Selection of Corrosion Monitoring Equipment for Subsea Safety Joint

OpenAIRE

Ramachandran, Sajini

2016-01-01

Master Thesis in Offshore technology: Industrial asset management In Nature, most of all Metals evolve as stable ores of chemical compounds like oxides, sulphides or carbonates. Lot of energy is required to refine and make them useful for some means for every Industry. Corrosion on metals can reverse an unnatural process back to a lower state of energy, easily as simple. It eats away metal in outdoor furniture and automotive bodies, leaving the surface with bad appearance and if it is n...

Joint IAEA/NEA IRS guidelines

International Nuclear Information System (INIS)

1997-01-01

The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants

The Sandia/Arzamas-16 Magazine-to-Magazine Remote Monitoring Field Trial Evaluation

International Nuclear Information System (INIS)

Barkanov, Boris; Blagin, Sergei; Croessmann, Dennis; Damico, Joe; Ehle, Steve; Nilsen, Curt

1999-01-01

Sandia National Laboratories and the Russian Federal Nuclear Center-All Russian Research Institute for Experimental Physics (VNIIEF) (also known as Arzamas-16) are collaborating on ways to assure the highest standards of safety, security, and international accountability of fissile material. For these collaborations, sensors and information technologies have been identified as important in reaching these standards in a cost-effective manner. Specifically, Sandia and VNIIEF have established a series of remote monitoring field trials to provide a mechanism for joint research and development on storage monitoring systems. These efforts consist of the ''Container-to-Container'', ''Magazine-to-Magazine'', and ''Facility-to-Facility'' field trials. This paper will describe the evaluation exercise Sandia and VNIIEF conducted on the Magazine-to-Magazine systems. Topics covered will include a description of the evaluation philosophy, how the various sensors and system features were tested, evaluation results, and lessons learned

Safety and Efficacy of NEXT-II®, a Novel Water-Soluble, Undenatured Type II Collagen inHealthy Human SubjectsSuffering from Occasional Knee Joint Pain

Directory of Open Access Journals (Sweden)

Orie Yoshinari

2015-07-01

Full Text Available Background: Oral administration of a novel water-soluble undenatured type II collagen (NEXT-II® has been demonstrated to ameliorate the signs and symptoms of rheumatoid arthritis (RA in animal models. In the present investigation, we conducted a pilot study to examine the efficacy and safety of NEXT-II® in borderline subjects defined as healthy and non-diseased state, but with potential risks in knee joint health. Method: We employed Western Ontario McMaster Index (WOMAC score and Visual Analog Scale (VAS scores to assess the extent of improvement in the knee joints in these volunteers following supplementation of 40 mg NEXT-II® (10 mg as undenatured type II collagen over a period of 12 weeks. Result: The results demonstrated that NEXT-II® treatment significantly reduced WOMAC and VAS scores compared to subjects at baseline. Specifically, in the evaluation using VAS, the borderline subjects at resting, walking, and going up and down the stairs revealed significant improvement when compared to the baseline. Conclusion: The results of the studies demonstrated that NEXT-II® might be an ingredient which is safe and effective in the application of dietary supplement in ameliorating joint pain and symptoms of the borderline subjects without any adverse events.

Expansion joints for LMFBR

International Nuclear Information System (INIS)

Dzenus, M.; Hundhausen, W.; Jansing, W.

1980-01-01

This discourse recounts efforts put into the SNR-2 project; specifically the development of compensation devices. The various prototypes of these compensation devices are described and the state of the development reviewed. Large Na (sodium)-heat transfer systems require a lot of valuable space if the component lay-out does not include compensation devices. So, in order to condense the spatial requirement as much as possible, expansion joints must be integrated into the pipe system. There are two basic types to suit the purpose: axial expansion joints and angular expansion joints. The expansion joints were developed on the basis of specific design criteria whereby differentiation is made between expansion joints of small and large nominal diameter. Expansion joints for installation in the sodium-filled primary piping are equipped with safety bellows in addition to the actual working bellows. Expansion joints must be designed and mounted in a manner to completely withstand seismic forces. The design must exclude any damage to the bellows during intermittent operations, that is, when sodium is drained the bellows' folds must be completely empty; otherwise residual solidified sodium could destroy the bellows when restarting. The expansion joints must be engineered on the basis of the following design data for the secondary system of the SNR project: working pressure: 16 bar; failure mode pressure: 5 events; failure mode: 5 sec., 28.5 bar, 520 deg. C; working temperature: 520 deg. C; temperature transients: 30 deg. C/sec.; service life: 200,000 h; number of load cycles: 10 4 ; material: 1.4948 or 1.4919; layer thickness of folds: 0.5 mm; angular deflection (DN 800): +3 deg. C or; axial expansion absorption (DN 600): ±80 mm; calculation: ASME class. The bellows' development work is not handled within this scope. The bellows are supplied by leading manufacturers, and warrant highest quality. Multiple bellows were selected on the basis of maximum elasticity - a property

Experimental investigation on full scale RC beam-column joint of NPP structures

International Nuclear Information System (INIS)

Thandavamoorthy, T.S.; Lakshmanan, N.; Reddy, G.R.; Kushwaha, H.S.

2003-01-01

The Nuclear Power Plant (NPP) structures in India are constructed using reinforced concrete. The beam-column joint in these structures are critical sub-assemblages because they ensure continuity of a structure and transfer forces from one element to another. Under seismic excitation, the beam-column joint region is subjected to horizontal and vertical shear forces whose magnitudes are typically many times higher than those within the adjacent beams and columns. In view of the increased incidence of seismicity in the country, the safety of these structures against earthquake loading assumes greater significance. There is a growing need to look into the seismic safety aspect of existing RC frame type structures in NPPs, which have been designed as per codes prevalent at the time of their construction. Seismic performance of such joints has not been studied extensively in India. Therefore experimental testing of full scale joint identical to those available in the existing NPP structures, was carried out to study its behaviour and evaluate its capacity. The size of the beam of the joint was 2000 mm x 610 mm x 915 mm and column 2915 mm x 610 mm x 915 mm. The percentage reinforcement of the beam was 4.95 and column 1.5. Such full scale and heavily reinforced concrete joint was cast successfully in the laboratory and tested under monotonic loading. The paper presents a complete description of the experimental testing, observations made during testing as for cracking, deflection and rotation of joint, discussion of results obtained, etc. Conclusions drawn from the investigation are also presented. (author)

The development of condition monitoring for the safety of rotating machine in PWR using motor current signature analysis

International Nuclear Information System (INIS)

Syaiful Bakhri

2013-01-01

Condition monitoring of rotating machine is essential to guarantee the safety operation as well as to improve the efficiency of nuclear power plants operations. One of the promising condition monitoring techniques which has been preferred currently since it is simple, non-invasive and inexpensive is Motor Stator Signature Analysis (MCSA). However, the investigation of the MCSA technique using a compact, low cost, and having industrial class hardware which is capable for nuclear power plant applications has been limited. The research is aimed to develop condition monitoring method based on MCSA utilizing a compact industrial class for nuclear power plant. The investigation includes development of condition monitoring based on real-time FPGA-CompatRIO hardware, development of a custom built display module for early warning system, testing of the monitoring hardware, fault frequency analysis of electric motors including the performances of fault detections. The condition monitoring system is able to execute a fault detection task around 164 ms, to recognize accurately fault frequencies of stator shorted turn for about 75%, broken rotor bar around 95%, eccentricity 65%, mechanical misalignment 85%, including supply voltage unbalances 100%. The condition monitoring system based on its performance assessments could become a suitable alternative not only for rotating machines but also condition monitoring for other nuclear reactor components. (author)

Structural FEM analysis of the strut-to-fuselage joint of a two-seat composite aircraft

International Nuclear Information System (INIS)

Vargas-Rojas, Erik; Camarena-Arellano, Diego; Hernández-Moreno, Hilario

2014-01-01

An analysis of a strut-to-fuselage joint is realized in order to evaluate the zones with a high probability of failure by means of a safety factor. The whole section is analyzed using the Finite Element Method (FEM) so as to estimate static resistance behavior, therefore it is necessary a numerical mock-up of the section, the mechanical properties of the Carbon-Epoxy (C-Ep) material, and to evaluate the applied loads. Results of the analysis show that the zones with higher probability of failure are found around the wing strut and the fuselage joint, with a safety factor lower than expected in comparison with the average safety factor used on aircrafts built mostly with metals

Design and implementation of an online risk monitor

International Nuclear Information System (INIS)

Majdara, A.; Nematollah, M. R.; Haddad, K.; Sepanloo, K.

2006-01-01

Probabilistic Safety Assessment is a powerful method for evaluating the safety of nuclear facilities. Probabilistic Safety Assessment models are the basis of online risk monitors, which can be utilized for monitoring the online risk. In this paper a newly developed risk monitor called Safety Assessment Tool is presented, and its main features and capabilities are introduced. Some of these features are: graphical event/fault tree developing interface, a 30-day risk profile, performing importance analysis, different administrative levels, and handling time dependent failure data. Safety Assessment Tool can be utilized in nuclear power plants, research reactors, etc. as an online assistant to manage safety issues and prevent high-risk configurations

Monitoring total-body inflammation and damage in joints and entheses

DEFF Research Database (Denmark)

Axelsen, M. B.; Eshed, I.; Østergaard, M.

2017-01-01

Objective: To investigate changes in whole-body magnetic resonance imaging (WBMRI) inflammatory and structural lesions in most joints and entheses in patients with rheumatoid arthritis (RA) treated with adalimumab. Methods: WBMRI was obtained at weeks 0, 6, 16, and 52 in a 52 week follow-up study...

Developing Digital Image Techniques with Low-Cost Unmanned Mobile to Monitor the Safety of Dam and Affiliated Structure

Science.gov (United States)

Sung, Wen-Pei; Shih, Ming-Hsiang

2016-04-01

Global warming phenomena are increasingly serious, the El Niño and La Niña continue to occur repeatedly, causing the irregular drought and flood problem repeatedly. Mountain form of Taiwan is steep and storage ability of rainwater is insufficient to supply the livelihood of people and usage of industry which need to rely on rainwater reservoir. Thus, to ensure the water supply and self-reliance energy supply, one of ways to keep water resource is to build reservoir. Nevertheless, Taiwan is located on Pacific seismic belt; additionally, geological conditions are not fine, over-developed in the hills lead to more natural disasters in the future. Thus, strong shakes and typhoons which caused a degree of severe landslides around dam lead to reduce catchment of dam to result in affecting the safety of dam. Otherwise, the cracks and rusts in dam, induced by the defects of material, bad construction and seismic excitation respectively, thus, the mechanics phenomena of dam and its affiliated structures with crack are probing into the cause of stress concentration, induced high crack increase rate, affect the safety and usage of dam. This research is aimed at the safety evaluation technique of dam and its affiliated structures to develop three dimensional digital image correlation techniques for monitoring the safety of dam and its affiliated structures. Namely, developing the unmanned mobile on two axis of digital image correlation method is to detect the digital images from geometric scanning techniques for dam structure. This developed technique combined with Unmanned Aerial Vehicle (UAV) to develop the near filed scanning and monitoring techniques for local deformation and cracks on dam and its affiliated structures.

Joint WHO/ISH workshop on efficacy and radiation safety in interventional radiology

International Nuclear Information System (INIS)

Baeuml, A.; Bauer, B.; Bernhardt, J.H.; Stieve, F.E.; Veit, R.; Zeitlberger, I.

1997-02-01

With the constantly developing technology and the opening of new fields of application, the implementation of Interventional Radiology (IR) is increasing considerably. These sophisticated procedures can frequently replace open surgery, and this is of enormous benefit for the patient. On the other hand, IR involves prolonged application of fluoroscopy and - due to the need for excellent image quality - partly very high dose-rate levels. Additionally, cine-series, and alsogreat numbers of single radiographs are necessary. Accordingly, the levels of exposure to patients and staff are very high. In order to consider possible reduction of the radiation risks of IR procedures interdiciplinary talks between representatives of manufacturers of X-ray equipment, hospital physicists and the clinical community would seem necessary in order to find ways of avoiding unproductive radiation exposure to the patient and to clinical staff. This was the aim of a workshop on IR, which was jointly organized by the World Health Organization and the Institute of Radiation Hygiene of the Federal Office for Radiation Protection in Germany in October 1995. It was intended as a forum for the discussion of issues related to IR, and to forster improved application, that is to say as an opportunity: To present the state of the art; to work out proposals for more efficient clinical protocols; to discuss on schemes of education and training and on equipment-related developments. Improvement of radiation safety for both patients and staff, was the general aim of the workshop. This volume contains the presentations given on the first day of the workshop. (orig./DG) [de

Perspectives on dam safety in Canada

International Nuclear Information System (INIS)

Halliday, R.

2004-01-01

Canadian dam safety issues were reviewed from the perspective of a water resources engineer who is not a dam safety practitioner. Several external factors affecting dam safety were identified along with perceived problems in dam safety administration. The author claims that the main weakness in safety practices can be attributed to provincial oversights and lack of federal engagement. Some additions to the Canadian Dam Safety Guidelines were proposed to address these weaknesses. Canada has hundreds of large dams and high hazard dams whose failure would result in severe downstream consequences. The safety of dams built on boundary waters shared with the United States have gained particular attention from the International Joint Commission. This paper also examined safety criteria for concerns such as aging dams, sabotage and global climate change that may compromise the safety of a dam. 26 refs

Hospital safety climate and safety behavior: A social exchange perspective.

Science.gov (United States)

Ancarani, Alessandro; Di Mauro, Carmela; Giammanco, Maria D

Safety climate is considered beneficial to the improvement of hospital safety outcomes. Nevertheless, the relations between two of its key constituents, namely those stemming from leader-subordinate relations and coworker support for safety, are still to be fully ascertained. This article uses the theoretical lens of Social Exchange Theory to study the joint impact of leader-member exchange in the safety sphere and coworker support for safety on safety-related behavior at the hospital ward level. Social exchange constructs are further related to the existence of a shame-/blame-free environment, seen as a potential antecedent of safety behavior. A cross-sectional study including 166 inpatients in hospital wards belonging to 10 public hospitals in Italy was undertaken to test the hypotheses developed. Hypothesized relations have been analyzed through a fully mediated multilevel structural equation model. This methodology allows studying behavior at the individual level, while keeping into account the heterogeneity among hospital specialties. Results suggest that the linkage between leader support for safety and individual safety behavior is mediated by coworker support on safety issues and by the creation of a shame-free environment. These findings call for the creation of a safety climate in which managerial efforts should be directed not only to the provision of new safety resources and the enforcement of safety rules but also to the encouragement of teamwork and freedom to report errors as ways to foster the capacity of the staff to communicate, share, and learn from each other.

TH-C-18C-01: MRI Safety

Energy Technology Data Exchange (ETDEWEB)

Pooley, R [Mayo Clinic, Jacksonville, FL (United States); Bernstein, M; Shu, Y; Gorny, K; Felmlee, J [Mayo Clinic, Rochester, MN (United States); Panda, A [Mayo Clinic, Arizona, Scottsdale, AZ (United States)

2014-06-15

Clinical diagnostic medical physicists may be responsible for implementing and maintaining a comprehensive MR safety program. Accrediting bodies including the ACR, IAC, Radsite and The Joint Commission each include aspects of MR Safety into their imaging accreditation programs; MIPPA regulations further raise the significance of non-compliance. In addition, The Joint Commission recently announced New and Revised Diagnostic Imaging Standards for accredited health care organizations which include aspects of MR Safety. Hospitals and clinics look to the physicist to understand guidelines, regulations and accreditation requirements related to MR safety. The clinical medical physicist plays a significant role in a clinical practice by understanding the physical basis for the risks and acting as a facilitator to successfully implement a safety program that provides well-planned siting, allows for the safe scanning of certain implanted devices, and helps radiologists manage specific patient exams. The MRI scanning of specific devices will be discussed including cardiac pacemakers and neurostimulators such as deep brain stimulators. Furthermore for sites involved in MR guided interventional procedures, the MR physicist plays an essential role to establish safe practices. Creating a framework for a safe MRI practice includes the review of actual safety incidents or close calls to determine methods for prevention in the future. Learning Objectives: Understand the requirements and recommendations related to MR safety from accrediting bodies and federal regulations. Understand the Medical Physicist's roles to ensure MR Safety. Identify best practices for dealing with implanted devices, including pacemakers and deep brain stimulators. Review aspects of MR safety involved in an MR guided interventional environment. Understand the important MR safety aspects in actual safety incidents or near misses.

Tritium Room Air Monitor Operating Experience Review

Energy Technology Data Exchange (ETDEWEB)

L. C. Cadwallader; B. J. Denny

2008-09-01

Monitoring the breathing air in tritium facility rooms for airborne tritium is a radiological safety requirement and a best practice for personnel safety. Besides audible alarms for room evacuation, these monitors often send signals for process shutdown, ventilation isolation, and cleanup system actuation to mitigate releases and prevent tritium spread to the environment. Therefore, these monitors are important not only to personnel safety but also to public safety and environmental protection. This paper presents an operating experience review of tritium monitor performance on demand during small (1 mCi to 1 Ci) operational releases, and intentional airborne inroom tritium release tests. The tritium tests provide monitor operation data to allow calculation of a statistical estimate for the reliability of monitors annunciating in actual tritium gas airborne release situations. The data show a failure to operate rate of 3.5E-06/monitor-hr with an upper bound of 4.7E-06, a failure to alarm on demand rate of 1.4E-02/demand with an upper bound of 4.4E-02, and a spurious alarm rate of 0.1 to 0.2/monitor-yr.

Treatment of lumbar facet joint syndrome by CT-guided intraarticular infiltration of fact joints

International Nuclear Information System (INIS)

Schleifer, J.; Fenzl, G.; Wolf, A.; Diehl, K.

1994-01-01

In 62 patients with facet syndrome a total of 205 joints were infiltrated, CT monitoring being used in all cases. Each facet joint was infiltrated with 0.3 ml bupivacaine and 0.8 ml methylprednisolone. The patients were divided into three groups. Group 1 consisted of 24 persons who had undergone lumbar disc surgery, group 2 of 23 patients with spondylarthrosis of the facet joints, and group 3 of 15 patients who had undergone lumbar disc surgery but hat additional spondylarthrosis. Very good results were defined as pain relief for longer than 4 weeks, good results as pain relief for up to 4 weeks and poor results as brief pain relief or none at all. In 27 patients facet infiltration was performed for the purpose of diagnosis. Results were significantly in group 2 than in group 1. In group 3 results were better than in group 1, but worse than in group 2. These differences were not statistical by significant. Seven patients in the diagnostic group had no pain relief, and facet syndrome was excluded. (orig.) [de

Radiation safety: New international standards

International Nuclear Information System (INIS)

Gonzalez, A.J.

1994-01-01

This article highlights an important result of this work for the international harmonization of radiation safety: specifically, it present an overview of the forthcoming International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources - the so-called BSS. They have been jointly developed by six organizations - the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the Nuclear Energy Agency of the Organization for Economic Co-operation and Development (NEA/OECD), the Pan American Health Organization (PAHO), and the World Health Organization (WHO)

Tools for plant safety engineer

International Nuclear Information System (INIS)

Fabic, S.

1996-01-01

This paper contains: - review of tools for monitoring plant safety equipment reliability and readiness, before and accident (performance indicators for monitoring the risk and reliability performance and for determining when degraded performance alert levels are achieved) - brief reviews of tools for use during an accident: Emergency Operating Procedures (EOPs), Emergency Response Data System (ERDS), Reactor Safety Assessment System (RSAS), Computerized Accident Management Support

Marine mammal observations collected by aircraft and ship and submitted as part of the ConocoPhillips and Shell Joint Monitoring Program in the Chukchi and Beaufort Seas, 2006-2007 (NODC Accession 0120531)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set was collected as part of the Joint Monitoring Program during seismic activities in the Chukchi Sea. The 2006 data was collected by ship and aircraft as...

Management of safety, safety culture and self assessment

International Nuclear Information System (INIS)

Carnino, A.

2000-01-01

Safety management is the term used for the measures required to ensure that an acceptable level of safety is maintained throughout the life of an installation, including decommissioning. The safety culture concept and its implementation are described in part one of the paper. The principles of safety are now quite well known and are implemented worldwide. It leads to a situation where harmonization is being achieved as indicated by the entry into force of the Convention on Nuclear Safety. To go beyond the present nuclear safety levels, management of safety and safety culture will be the means for achieving progress. Recent events which took place in major nuclear power countries have shown the importance of the management and the consequences on safety. At the same time, electricity deregulation is coming and will impact on safety through reductions in staffing and in operation and maintenance cost at nuclear installations. Management of safety as well as its control and monitoring by the safety authorities become a key to the future of nuclear energy.(author)

Problems in Food Safety of Hunan Province and Countermeasures

Institute of Scientific and Technical Information of China (English)

Fanfan; OUYANG; Fangming; DENG

2014-01-01

In recent years,serious food safety accidents are of frequent occurrence. Although government has taken many practical and feasible measures to contain food safety accidents,new food safety accidents still emerge in large numbers. In this situation,food safety control is a long-term and arduous task to be performed jointly by many government departments. Finally,it presents corresponding countermeasures and recommendations on the basis of current situations of food safety in Hunan Province,problem causes,in combination with control measures related to food safety both at home and abroad.

Perspectives of local diclofenacol 1% liniment application in joint diseases

Directory of Open Access Journals (Sweden)

R M Balabanova

2003-01-01

Full Text Available Objective. To assess efficacy and safety diclofenacol 1% liniment application in comparison with diclo- ran plus. Material and methods. An open controlled 2-weeks trial of diclofenacol 1% liniment on 30 pts with active joint syndrome (group 1 compared with dicloran plus 1% gel on 20 pts (group II. Pts age ranged from 16 to 79 years, mean disease duration was 8,2 1,5 years. Most pts had II activity degree. Results. Diclofenacol 1% liniment applications decreased pain at rest and at movement and circle of aim joints. In pts with RA effect was more prominent. Dicloran plus provided equivalent results. Local effect of diclofenacol appeared in average after 31,5 min. (from 10 to 73 min and lasted during 118,3 min (from 50 to 240 min.. Diclofenacol allowed to decrease dose of oral NSAIDs in 43,3% of pts and dicloran - in 40% of pts. Diclofenacol safety was good without local and systemic adverse events. Conclusion. Diclofenacol 1% liniment manufactured by Hiperion S.A. (Rumania can be recommended for wide administration in treatment of joint diseases particularly in pts with concomitant gastrointestinal diseases and hypertension.

Statement at Fukushima Ministerial Conference on Nuclear Safety, 15 December 2012, Koriyama City, Fukushima Prefecture, Japan

International Nuclear Information System (INIS)

Amano, Y.

2012-01-01

When disaster struck at the Fukushima Daiichi Nuclear Power Plant in March 2011, the IAEA offered immediate assistance to the Plant operators and the Japanese authorities as they tried to regain control over the reactors. We began sharing verified information about the accident with the world and helped to channel international assistance to Japan. A high priority was to do everything we could to help ensure the safety of the people of Japan, especially those in Fukushima Prefecture who were most affected by the crisis. I went to Japan a few days after the accident to meet then Prime Minister Kan. I assured him that Japan could count on the support of the entire international community and stressed the need for full transparency. I sent a number of expert teams to assist in areas such as radiological monitoring, food safety, and analysis of the situation at the Fukushima Daiichi Plant. Four IAEA teams undertook measurements in the Fukushima region, both inside and outside the 20 km evacuation zone. An expert on marine monitoring programmes from the IAEA Environmental Laboratories helped to monitor seawater. Joint teams from the IAEA and the UN Food and Agriculture Organization advised local authorities on technical issues related to food safety and agricultural countermeasures. Some important environmental readings at key points in the unfolding crisis were taken by IAEA experts. Our presence helped to provide reassurance to the people of Japan at a very critical time. It is now one year and nine months since the accident. In that time, we have continued to work closely with Japan. Today, I will sign an important document with Governor Sato of Fukushima Prefecture on our cooperation in the coming years. The IAEA will work closely with the Prefecture in radiation monitoring and decontamination. We will also implement human health projects with Fukushima Medical University.

Development of web monitoring radiation area monitor

International Nuclear Information System (INIS)

Jung, Hoon Jin; Lee, Jun Hee; Namkoong, Phil; Lee, Dong Hoon; Lee, Su Hong; Lee, Gun Bae

2005-01-01

Recently the increasing number of radioisotope industry and nuclear facility have ever raised the possibility of radiation safety accident. As such a result, radioisotope companies and nuclear facility operators have become to be much interested in radiation area monitoring for efficient radiation protection. At present, almost of the radiation area monitors which are imported products are outdated in aspect of their functions. Diversification of the monitoring work is urgently demanding additional functions to be added. Thus we have developed new-type digital area monitor which enables remote web monitoring with image and radiation dose rate value at distant places through using internet, the latest IT technology, and radiation measurement technology

Use of remote monitoring

Energy Technology Data Exchange (ETDEWEB)

Fournel, E; Gouilloux, C

1977-01-01

Paper traces the development of remote monitoring devices, since their first appearance for safety purposes. Discusses their uses in coal mines: working and safety (definitions); sources and channels of information (transmission of information by automatic or verbal means); mine control stations; duties and responsibilities of persons in charge. Examines the contribution made by remote monitoring to management in production sector. Gives examples of assistance given to production management showing a very advantageous result on balance, by their use. The use of computers in real time and in batched mode is compared. Discusses their use in monitoring mine atmosphere. Very favorable results have already been obtained in France and abroad. The broadening scope and future of remote monitoring is considered.

Safety and Effectiveness of Highly Active Antiretroviral Therapy in Treatment-Naïve HIV Patients: Preliminary Findings of a Cohort Event Monitoring Study in Belarus.

Science.gov (United States)

Setkina, Svetlana; Dotsenko, Marina; Bondar, Sviatlana; Charnysh, Iryna; Kuchko, Alla; Kaznacheeva, Alena; Kozorez, Elena; Dodaleva, Alena; Rossa, Natalia

2015-04-01

Antiretroviral drugs have well-documented evidence-based favorable benefit-risk ratios. Although various studies have investigated and characterized the safety profile of antiretroviral medicines, there are a limited number of studies evaluating the safety of first-line antiretroviral therapy (ART) in patients with a specific co-morbidity. A cohort event monitoring (CEM) study of the safety and effectiveness of antiretroviral medicines in a target population that has a significant level of co-morbidities (chronic infectious diseases, peripheral blood cytopenias) was implemented. The aim was to evaluate the safety profile of the highly active ART (HAART) in the target population and subpopulations with risk factors, to optimize the monitoring and decision-making procedure for subgroups of patients with specific types of co-morbidity, and to implement a more vigilant approach to therapy management in risk groups of patients. Prospective observational CEM was implemented among HAART-naïve HIV-positive patients at four clinical sites from December 2012. Eligible patients were those starting first-line HAART. Close medical supervision of all enrolled patients, with regular clinical and laboratory monitoring, was provided by healthcare professionals within 1 year after commencement of therapy. Standardized forms were used for data collection on initial and subsequent visits. All objective or subjective deviations in condition (events) were assessed for a causal relationship with ART, and for severity, seriousness, reversibility, preventability, and pre-existing risk factors in the case of adverse drug reactions (ADRs). A total of 518 HAART-naïve HIV-positive patients were enrolled in the CEM study. Of these patients, 65% (337) experienced one or several ADRs related to one or more components of HAART. Most of the ADRs reported were non-serious, expected, common (very common), transient (correctable), or reversible. The most common were hematotoxic, hepatotoxic, and

Sacroiliac Joint Fusion: One Year Clinical and Radiographic Results Following Minimally Invasive Sacroiliac Joint Fusion Surgery.

Science.gov (United States)

Kube, Richard A; Muir, Jeffrey M

2016-01-01

Recalcitrant sacroiliac joint pain responds well to minimally-invasive surgical (MIS) techniques, although long-term radiographic and fusion data are limited. To evaluate the one-year clinical results from a cohort of patients with chronic sacroiliac (SI) joint pain unresponsive to conservative therapies who have undergone minimally invasive SI joint fusion. SI joint fusion was performed between May 2011 and January 2014. Outcomes included radiographic assessment of fusion status, leg and back pain severity via visual analog scale (VAS), disability via Oswestry Disability Index (ODI) and complication rate. Outcomes were measured at baseline and at follow-up appointments 6 months and 12 months post-procedure. Twenty minimally invasive SI joint fusion procedures were performed on 18 patients (mean age: 47.2 (14.2), mean BMI: 29.4 (5.3), 56% female). At 12 months, the overall fusion rate was 88%. Back and leg pain improved from 81.7 to 44.1 points (p<0.001) and from 63.6 to 27.7 points (p=0.001), respectively. Disability scores improved from 61.0 to 40.5 (p=0.009). Despite a cohort containing patients with multiple comorbidities and work-related injuries, eight patients (50%) achieved the minimal clinically important difference (MCID) in back pain at 12 months, with 9 (69%) patients realizing this improvement in leg pain and 8 (57%) realizing the MCID in ODI scores at 12 months. No major complications were reported. Minimally invasive SI joint surgery is a safe and effective procedure, with a high fusion rate, a satisfactory safety profile and significant improvements in pain severity and disability reported through 12 months post-procedure.

Nuclear safety. How is it evaluated?

International Nuclear Information System (INIS)

Andersson, Kjell; Andersson, Johan; Carlsson, Lennart; Olsson, Richard; Ericsson, A.M.; Gunsell, L.; Wene, C.O.

1996-09-01

A working group with representatives for the three subject areas reactor safety, disposal of spent fuels and transport of radioactive materials has performed a project aiming to clarify similarities and differences of the three areas concerning methods for safety analysis, criteria, risks etc; and to develop contacts between experts in the areas in order to facilitate transfer of methods. Some of the more precise objectives were: To identify common problems that could be solved jointly, to discuss prospects for a 'meta-method' that can support safety analysis in the entire field of nuclear safety, and to discuss possibilities for a homogeneous attitude towards risk management

Proceedings of the 5. Regional congress on radiation protection and safety; 2. Iberian and Latin American Congress on Radiological Protection Societies; Regional IRPA Congress

International Nuclear Information System (INIS)

2001-01-01

The Fifth Regional Congress on Radiation Protection and Nuclear Safety has been held in Recife (Brazil), from 29th April to 4th May 2001. The congress was hosted by the Brazilian Radiation Protection Society, under the joint sponsorship of FRALC and UFPE-DEN Department of Nuclear Energy. Its designation as a Regional IRPA Congress has been requested. The main purpose of the meeting was to bring together professionals from the industry, universities and research laboratories to present and discuss the latest research results, and to review the state of the art on applied and fundamental aspects of the radiation protection. These specialists have talked about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. In their discussions, also were included subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation

Discussion on joint operation of wind farm and pumped-storage hydroplant

Science.gov (United States)

Li, Caifang; Wu, Yichun; Liang, Hao; Li, Miao

2017-12-01

Due to the random fluctuations in wind power, large amounts of grid integration will have a negative impact on grid operation and the consumers. The joint operation with pumped-storage hydroplant with good peak shaving performance can effectively reduce the negative impact on the safety and economic operation of power grid, and improve the utilization of wind power. In addition, joint operation can achieve the optimization of green power and improve the comprehensive economic benefits. Actually, the rational profit distribution of joint operation is the premise of sustainable and stable cooperation. This paper focuses on the profit distribution of joint operation, and applies improved shapely value method, which taking the investments and the contributions of each participant in the cooperation into account, to determine the profit distribution. Moreover, the distribution scheme can provide an effective reference for the actual joint operation of wind farm and pumped-storage hydroplant.

10 CFR 34.47 - Personnel monitoring.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Personnel monitoring. 34.47 Section 34.47 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Radiation Safety Requirements § 34.47 Personnel monitoring. (a) The licensee may not...

Safety and effectiveness of minimally invasive sacroiliac joint fusion in women with persistent post-partum posterior pelvic girdle pain: 12-month outcomes from a prospective, multi-center trial.

Science.gov (United States)

Capobianco, Robyn; Cher, Daniel

2015-01-01

Postpartum posterior pelvic girdle pain (PPGP) affects nearly 20 % of women who experience back pain in the peripartum period. The sacroiliac joint is a source of this pain in 75 % of women with persistent PPGP. A subset of women will fail to obtain acceptable pain relief from the current array of non-surgical treatment options. The purpose of this study is to assess the safety and effectiveness of minimally invasive sacroiliac (SI) joint fusion in women with chronic SI joint dysfunction whose pain began in the peri-partum period whose symptoms were recalcitrant to non-surgical management. A sub-group analysis of subjects with sacroiliac joint disruption and/or degenerative sacroiliitis enrolled in a prospective, multi-center trial of SI joint fusion was performed. Subjects with PPGP were identified and compared with women without PPGP and with men. Of 172 enrolled subjects, 52 were male, 100 were females without PPGP and 20 females had PPGP. PPGP subjects were significantly younger (43.3 years, vs. 52.8 for females without PPGP and 50.5 for men, p = 0.002). There were no differences in any other demographic or baseline clinical measure. Women with PPGP experienced a significant improvement in pain (-51 mm on VAS), function (-20.6 pts on ODI) and quality of life (SF-36 PCS +10.4, MCS +7.2, EQ-5D +0.31) at 12 months after surgery. These improvements were characteristic of the overall study results; no difference was detected between sub-groups. The sacroiliac joint can be a source of pain in women with persistent PPGP and should be investigated as a pain generator. In this study, women with carefully diagnosed chronic SI joint pain from PPGP recalcitrant to conservative therapies experienced clinically beneficially improvements in pain, disability and quality of life after minimally invasive SI joint fusion using a series of triangular porous plasma spray coated implants.

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition); Surete radiologique en radiographie industrielle

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-05-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in Horizontal-Ellipsis shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Toward risk assessment 2.0: Safety supervisory control and model-based hazard monitoring for risk-informed safety interventions

International Nuclear Information System (INIS)

Favarò, Francesca M.; Saleh, Joseph H.

2016-01-01

Probabilistic Risk Assessment (PRA) is a staple in the engineering risk community, and it has become to some extent synonymous with the entire quantitative risk assessment undertaking. Limitations of PRA continue to occupy researchers, and workarounds are often proposed. After a brief review of this literature, we propose to address some of PRA's limitations by developing a novel framework and analytical tools for model-based system safety, or safety supervisory control, to guide safety interventions and support a dynamic approach to risk assessment and accident prevention. Our work shifts the emphasis from the pervading probabilistic mindset in risk assessment toward the notions of danger indices and hazard temporal contingency. The framework and tools here developed are grounded in Control Theory and make use of the state-space formalism in modeling dynamical systems. We show that the use of state variables enables the definition of metrics for accident escalation, termed hazard levels or danger indices, which measure the “proximity” of the system state to adverse events, and we illustrate the development of such indices. Monitoring of the hazard levels provides diagnostic information to support both on-line and off-line safety interventions. For example, we show how the application of the proposed tools to a rejected takeoff scenario provides new insight to support pilots’ go/no-go decisions. Furthermore, we augment the traditional state-space equations with a hazard equation and use the latter to estimate the times at which critical thresholds for the hazard level are (b)reached. This estimation process provides important prognostic information and produces a proxy for a time-to-accident metric or advance notice for an impending adverse event. The ability to estimate these two hazard coordinates, danger index and time-to-accident, offers many possibilities for informing system control strategies and improving accident prevention and risk mitigation

Hybrid causal methodology and software platform for probabilistic risk assessment and safety monitoring of socio-technical systems

Energy Technology Data Exchange (ETDEWEB)

Groth, Katrina, E-mail: kgroth@umd.ed [Center for Risk and Reliability, 0151 Glenn L. Martin Hall, University of Maryland, College Park, MD 20742 (United States); Wang Chengdong; Mosleh, Ali [Center for Risk and Reliability, 0151 Glenn L. Martin Hall, University of Maryland, College Park, MD 20742 (United States)

2010-12-15

This paper introduces an integrated framework and software platform for probabilistic risk assessment (PRA) and safety monitoring of complex socio-technical systems. An overview of the three-layer hybrid causal logic (HCL) modeling approach and corresponding algorithms, implemented in the Trilith software platform, are provided. The HCL approach enhances typical PRA methods by quantitatively including the influence of soft causal factors introduced by human and organizational aspects of a system. The framework allows different modeling techniques to be used for different aspects of the socio-technical system. The HCL approach combines the power of traditional event sequence diagram (ESD)event tree (ET) and fault tree (FT) techniques for modeling deterministic causal paths, with the flexibility of Bayesian belief networks for modeling non-deterministic cause-effect relationships among system elements (suitable for modeling human and organizational influences). Trilith enables analysts to construct HCL models and perform quantitative risk assessment and management of complex systems. The risk management capabilities included are HCL-based risk importance measures, hazard identification and ranking, precursor analysis, safety indicator monitoring, and root cause analysis. This paper describes the capabilities of the Trilith platform and power of the HCL algorithm by use of example risk models for a type of aviation accident (aircraft taking off from the wrong runway).

Hybrid causal methodology and software platform for probabilistic risk assessment and safety monitoring of socio-technical systems

International Nuclear Information System (INIS)

Groth, Katrina; Wang Chengdong; Mosleh, Ali

2010-01-01

This paper introduces an integrated framework and software platform for probabilistic risk assessment (PRA) and safety monitoring of complex socio-technical systems. An overview of the three-layer hybrid causal logic (HCL) modeling approach and corresponding algorithms, implemented in the Trilith software platform, are provided. The HCL approach enhances typical PRA methods by quantitatively including the influence of soft causal factors introduced by human and organizational aspects of a system. The framework allows different modeling techniques to be used for different aspects of the socio-technical system. The HCL approach combines the power of traditional event sequence diagram (ESD)event tree (ET) and fault tree (FT) techniques for modeling deterministic causal paths, with the flexibility of Bayesian belief networks for modeling non-deterministic cause-effect relationships among system elements (suitable for modeling human and organizational influences). Trilith enables analysts to construct HCL models and perform quantitative risk assessment and management of complex systems. The risk management capabilities included are HCL-based risk importance measures, hazard identification and ranking, precursor analysis, safety indicator monitoring, and root cause analysis. This paper describes the capabilities of the Trilith platform and power of the HCL algorithm by use of example risk models for a type of aviation accident (aircraft taking off from the wrong runway).

Establishment of joint application system of safety analysis codes between Korea and Vietnam

International Nuclear Information System (INIS)

Chung, Bub Dong; Kim, Kyung Doo; Park, Cheol; Bae, Sung Won; Baek, Won Pil; Song, Cheol hwa; Jeong, Jae Jun; Lee, Seung Wook; Hwang, Moon Kyu; Lee, Chang Sup

2011-04-01

The following KAERI-VAEI collaboration works have been performed during the 2 year project ('09.4∼'11.4). 1) On the job training of Vietnam code users(1st training for 4 VAEI staff-3 months. 2nd training for 3 VAEI staff- 3 month), 2) Lecture of nuclear safety analysis (30 hrs basic course and 30 hrs advanced course), 3) Review of safety analysis method (IAEA safety concept and requirements), 4) Collaborative assessment of safety analysis code MARS (13 conceptual problem, 2 separate effect test problem, 1 integral effect test problem), 5) Input deck preparation of standard PWR (Preparation of APR1400 input deck and safety analysis of DBA). VAEI staffs have been familiarized to Korean PWR safety assessment technology through the collaboration assessment work using a computer code developed in Korea. The lectures for Vietnamese research will be contributed to the utilization and cultivation of Korean safety technology. The collaborated assessment works will be used for the establishment of MARS based safety analysis system which is independent from US safety assessment system

Establishment of joint application system of safety analysis codes between Korea and Vietnam

Energy Technology Data Exchange (ETDEWEB)

Chung, Bub Dong; Kim, Kyung Doo; Park, Cheol; Bae, Sung Won; Baek, Won Pil; Song, Cheol hwa; Jeong, Jae Jun; Lee, Seung Wook; Hwang, Moon Kyu; Lee, Chang Sup [KAERI, Daejeon (Korea, Republic of)

2011-04-15

The following KAERI-VAEI collaboration works have been performed during the 2 year project ('09.4{approx}'11.4). 1) On the job training of Vietnam code users(1st training for 4 VAEI staff-3 months. 2nd training for 3 VAEI staff- 3 month), 2) Lecture of nuclear safety analysis (30 hrs basic course and 30 hrs advanced course), 3) Review of safety analysis method (IAEA safety concept and requirements), 4) Collaborative assessment of safety analysis code MARS (13 conceptual problem, 2 separate effect test problem, 1 integral effect test problem), 5) Input deck preparation of standard PWR (Preparation of APR1400 input deck and safety analysis of DBA). VAEI staffs have been familiarized to Korean PWR safety assessment technology through the collaboration assessment work using a computer code developed in Korea. The lectures for Vietnamese research will be contributed to the utilization and cultivation of Korean safety technology. The collaborated assessment works will be used for the establishment of MARS based safety analysis system which is independent from US safety assessment system

Method of Fusion Diagnosis for Dam Service Status Based on Joint Distribution Function of Multiple Points

Directory of Open Access Journals (Sweden)

Zhenxiang Jiang

2016-01-01

Full Text Available The traditional methods of diagnosing dam service status are always suitable for single measuring point. These methods also reflect the local status of dams without merging multisource data effectively, which is not suitable for diagnosing overall service. This study proposes a new method involving multiple points to diagnose dam service status based on joint distribution function. The function, including monitoring data of multiple points, can be established with t-copula function. Therefore, the possibility, which is an important fusing value in different measuring combinations, can be calculated, and the corresponding diagnosing criterion is established with typical small probability theory. Engineering case study indicates that the fusion diagnosis method can be conducted in real time and the abnormal point can be detected, thereby providing a new early warning method for engineering safety.

Committee on the safety of nuclear installations - Operating plan (2006 - 2009)

International Nuclear Information System (INIS)

2007-01-01

In 2004, NEA issued its Strategic Plan covering the period 2005-2009, addressing the NEA activities associated with nuclear safety and regulation. Committee on the Safety of Nuclear Installations (CSNI) and Committee on Nuclear Regulatory Activities (CNRA), which have the primary responsibility for activities in this area, have developed and issued a joint strategic plan covering this same time period. As requested in the Joint Strategic Plan, each committee is to prepare an operating plan which describes in more detail the committee's organisation, planned activities, priorities and operating procedures to be used to implement the Joint Strategic Plan. In effect, the Joint Strategic Plan defines what type of work CSNI should do, whereas the Operating Plan describes the overall work scope and how to accomplish it to meet the joint CSNI/CNRA Strategic Plan objectives and mission. The present Operating Plan follows and takes into account the outcome of a CSNI assessment group, which has evaluated the CSNI activities. The assessment group expressed appreciation for the CSNI role and activity, while making recommendations with regards to scope of work and way to operate in order to further improve efficiency. The main objectives of CSNI are to: - Keep all member countries involved in and abreast of developments in safety technology. - Review operating experience with the objective to identify safety issues that need to be addressed by new research. - Review the state-of-knowledge on selected topics of nuclear safety technology and safety assessment. - Promote training and research projects that serve to maintain competence in nuclear safety matters. - Promote research as needed to reach consensus on nuclear safety issues of common interest. - Consider the safety implications of scientific and technical developments. To accomplish these objectives, CSNI is organised into six permanent working groups (as described in Section II), each covering a different set of

Robustness of structures- A report on a joint European project

NARCIS (Netherlands)

Faber, M.H.; Vrouwenvelder, A.C.W.M.; Sørensen, J.D.; Chryssanthopoulos, M.K.; Narasimhan, H.

2011-01-01

In 2005, the Joint Committee on Structural Safety (JCSS) together with Working Commission (WC) 1 of the International Association of Bridge and Structural Engineering (IABSE) organized a workshop on robustness of structures. Two important decisions resulted from this workshop, namely the development

Time-Lapse Joint Inversion of Cross-Well DC Resistivity and Seismic Data: A Numerical Investigation

Science.gov (United States)

Time-lapse joint inversion of geophysical data is required to image the evolution of oil reservoirs during production and enhanced oil recovery, CO2 sequestration, geothermal fields during production, and to monitor the evolution of contaminant plumes. Joint inversion schemes red...

Reliability data update using condition monitoring and prognostics in probabilistic safety assessment

Directory of Open Access Journals (Sweden)

Hyeonmin Kim

2015-03-01

Full Text Available Probabilistic safety assessment (PSA has had a significant role in quantitative decision-making by finding design and operational vulnerabilities and evaluating cost-benefit in improving such weak points. In particular, it has been widely used as the core methodology for risk-informed applications (RIAs. Even though the nature of PSA seeks realistic results, there are still “conservative” aspects. One of the sources for the conservatism is the assumptions of safety analysis and the estimation of failure frequency. Surveillance, diagnosis, and prognosis (SDP, utilizing massive databases and information technology, is worth highlighting in terms of its capability for alleviating the conservatism in conventional PSA. This article provides enabling techniques to solidify a method to provide time- and condition-dependent risks by integrating a conventional PSA model with condition monitoring and prognostics techniques. We will discuss how to integrate the results with frequency of initiating events (IEs and probability of basic events (BEs. Two illustrative examples will be introduced: (1 how the failure probability of a passive system can be evaluated under different plant conditions and (2 how the IE frequency for a steam generator tube rupture (SGTR can be updated in terms of operating time. We expect that the proposed model can take a role of annunciator to show the variation of core damage frequency (CDF depending on operational conditions.

Reliability data update using condition monitoring and prognostics in probabilistic safety assessment

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyeon Min; Lee, Sang Hwan; Park, Jun Seok; Kim, Hyung Dae; Chang, Yoon Suk; Heo, Gyun Young [Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of)

2015-03-15

Probabilistic safety assessment (PSA) has had a significant role in quantitative decision making by finding design and operational vulnerabilities and evaluating cost-benefit in improving such weak points. In particular, it has been widely used as the core methodology for risk-informed applications (RIAs). Even though the nature of PSA seeks realistic results, there are still 'conservative' aspects. One of the sources for the conservatism is the assumptions of safety analysis and the estimation of failure frequency. Surveillance, diagnosis, and prognosis (SDP), utilizing massive databases and information technology, is worth highlighting in terms of its capability for alleviating the conservatism in conventional PSA. This article provides enabling techniques to solidify a method to provide time and condition-dependent risks by integrating a conventional PSA model with condition monitoring and prognostics techniques. We will discuss how to integrate the results with frequency of initiating events (IEs) and probability of basic events (BEs). Two illustrative examples will be introduced: (1) how the failure probability of a passive system can be evaluated under different plant conditions and (2) how the IE frequency for a steam generator tube rupture (SGTR) can be updated in terms of operating time. We expect that the proposed model can take a role of annunciator to show the variation of core damage frequency (CDF) depending on operational conditions.

Equal Rights Monitor 2002

NARCIS (Netherlands)

Wil Portegijs; Annemarie Boelens; Saskia Keuzenkamp

2002-01-01

Original title: Emancipatiemonitor 2002. The Emancipation Monitor 2002 (Emancipatiemonitor 2002) provides statistics on the progress of the emancipation process, collected and analysed jointly by Statistics Netherlands (CBS) and the Netherlands Institute for Social Research/SCP. Is the

Appendix A.3. Minutes from meeting of the 1995th Joint Annual Report's Proposals and on the Slovak-Hungarian monitoring of underwater weir impacts according to the Inter-governmental Agreement held on October 10, 1996 in Gyoer

International Nuclear Information System (INIS)

1997-01-01

This part contains: (1) Points of the agenda: 1. Evaluation of the water discharged by the Slovak Party according to the Agreement from 1995; 2. Information about the monitoring data exchange: - surface and groundwater regimes in 1996, - surface and ground water quality, - soil moisture, - bio-monitoring including Proposals in the 1995 th Joint Annual Report; 3 Schedule of the 1995 th Joint Annual Report's proposals fulfillment; 4 Tasks concerning the 1996 th National and Annual Reports preparation. In the annexes tabular forms and digital formats for data exchange are presented: Surface water discharge; Surface water level; Surface water quality, Ground Water level; Ground Water quality; Soil moisture. (2) Annex 1: Minutes from meeting of experts for surface and ground water regime and quality held on September 11, 1996 in Bratislava. (3) Annex 2: Minutes from meeting of experts for soil moisture monitoring and biology held on October 2, 1996 in Mosonmagyarovar

10 CFR 39.65 - Personnel monitoring.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Personnel monitoring. 39.65 Section 39.65 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING Radiation Safety Requirements § 39.65 Personnel monitoring. (a) The licensee may not permit an individual to act as a logging...

Supervision of the safety culture in nuclear facilities

International Nuclear Information System (INIS)

2014-11-01

This brochure issued by the Swiss Federal Nuclear Safety Inspectorate ENSI reports on safety culture aspects in nuclear facilities and ENSI’s activities as a supervisory instance. ENSI is the independent supervisory authority for the nuclear sector in Switzerland. A definition of safety culture is presented and the development of the concepts used in its monitoring are discussed. The main attributes of a good safety culture are discussed. Further, the conceptual basics and principles of such monitoring are looked at and the methods used for the supervision of safety culture in nuclear facilities are described

MR arthrography: pharmacology, efficacy and safety in clinical trials

International Nuclear Information System (INIS)

Schulte-Altedorneburg, G.; Gebhard, M.; Wohlgemuth, W.A.; Fischer, W.; Zentner, J.; Bohndorf, K.; Wegener, R.; Balzer, T.

2003-01-01

A meta-analysis was carried out of clinical trials published between 1987 and 2001 in respect of the clinical pharmacology and safety as well as the diagnostic efficacy of gadolinium-DTPA (Gd-DTPA) for direct intra-articular injection before MRI examination.Design. Scientific papers (clinical, postmortem and experimental studies) and information from the manufacturer regarding intra-articular injection of Gd-DTPA that addressed questions of mode of action, optimal concentration and dose, elimination and safety were reviewed. Clinical studies were classified according to their study design. The sensitivity, specificity and accuracy of MR arthrography (MRA) were compared with a ''gold standard'' (arthroscopy, arthrotomy) and other radiological evidence for different joints.Results. Fifty-two clinical studies of the overall 112 studies addressed aspects of diagnostic efficacy of MRA in patients or in healthy volunteers. The shoulder was the most assessed joint (29 of 52 studies). Good (>80%) or even excellent (90-100%) sensitivity, specificity and accuracy were found for MRA in most indications, especially for the shoulder and knee joints and induced extension of rotator cuff lesions, labrum abnormalities and postoperative meniscal tears. Two millimoles per liter has proven to be the best concentration for intra-articular administration of Gd-DTPA. After passive complete diffusion from the joint within 6-24 h, complete and rapid renal elimination takes place after intra-articular injection. Local safety proved to be excellent after intra-articular administration of Gd-DTPA. Regarding systemic tolerance almost no side effects have been reported, but the same safety considerations apply for intra-articular administration of Gd-DTPA as for intravenous injection.Conclusions. The diagnostic efficacy of intra-articular MRA in most clinical conditions affecting major joints is greater than that of plain MRI. In some diagnostic problems MRA achieves almost the same

A monitor for consumer confidence in the safety of food

NARCIS (Netherlands)

Jonge, de J.

2008-01-01

Despite the fact that in the developed countries food safety standards are higher than ever, food safety incidents continue to occur frequently. The accumulation of food safety incidents might affect general consumer confidence in the safety of food. Therefore, in this thesis, the concept of general

Safety brings CERNois together

CERN Multimedia

CERN Bulletin

2012-01-01

The World Day for Health and Safety at Work, which was celebrated at CERN on 27 April, provided an opportunity for the safety professionals and members of the CERN personnel to get together to discuss joint concerns. It was a good opportunity for people to learn to distinguish between good and bad habits.   Members of the CERN Fire Brigade advise the Director-General. Two weeks ago, for the second year running, CERN’s restaurants hosted World Day for Health and Safety at Work stands. And once again, the stands attracted considerable interest. “Many people consulted our experts on safety issues relating in particular to ergonomics and electrical risks, the two themes to which we devoted particular attention this time,” explained Charles-Edouard Sala, a member of the BE Department’s Safety Unit and co-organiser of the event. The cardiac massage competition organised by members of CERN's Fire Brigade attracted a large number of competitors. No fe...

Proceedings of the NKS-R and NKS-B joint summary seminar

International Nuclear Information System (INIS)

Gwynn, J.P.; Isaksson, P.

2009-08-01

Nordic Nuclear Safety Research (NKS) is a platform for Nordic cooperation and competence in nuclear safety and related radiation protection issues including emergency preparedness and protection of the environment. Its purpose is to carry out joint activities producing seminars, exercises, scientific articles, technical reports and other types of reference material, with special efforts made to engage young scientists. The region in question is the five Nordic countries, i.e., Denmark (including the Faroe Islands and Greenland), Finland, Iceland, Norway and Sweden, who share a common cultural and historic heritage. The Nordic countries have cooperated in the field of nuclear safety for approximately half a century, developing informal networks for exchange of information, strengthening the region's potential for fast, coordinated and adequate response to nuclear threats, incidents and accidents. Activities are financed and supported by Nordic authorities, research institutions, power companies, contractors and other organizations, with results used by participating organizations in their decision making processes and information efforts.The NKS-R and NKS-B Joint Summary Seminar held at the Armemuseum, Stockholm on the 26th - 27th of March 2009 showcased a range of activities supported by NKS over the previous 2 years and provided an opportunity to bring together researchers and end users from the wider NKS community. This summary seminar was the first joint venture between the NKS-R and NKS-B Programmes since the current two programme format was adopted by NKS. One of our intentions in organising the Joint Summary Seminar was to further the reciprocal awareness of ongoing research and issues under the respective NKS-R and NKS-B Programmes, with the aim of promoting new networking opportunities and generating new ideas and approaches to solving existing problems. (au)

Proceedings of the NKS-R and NKS-B joint summary seminar

Energy Technology Data Exchange (ETDEWEB)

Gwynn, J.P.; Isaksson, P. (eds.) (Nordic Nuclear Safety Research, (NKS) (Denmark))

2009-08-15

Nordic Nuclear Safety Research (NKS) is a platform for Nordic cooperation and competence in nuclear safety and related radiation protection issues including emergency preparedness and protection of the environment. Its purpose is to carry out joint activities producing seminars, exercises, scientific articles, technical reports and other types of reference material, with special efforts made to engage young scientists. The region in question is the five Nordic countries, i.e., Denmark (including the Faroe Islands and Greenland), Finland, Iceland, Norway and Sweden, who share a common cultural and historic heritage. The Nordic countries have cooperated in the field of nuclear safety for approximately half a century, developing informal networks for exchange of information, strengthening the region's potential for fast, coordinated and adequate response to nuclear threats, incidents and accidents. Activities are financed and supported by Nordic authorities, research institutions, power companies, contractors and other organizations, with results used by participating organizations in their decision making processes and information efforts. The NKS-R and NKS-B Joint Summary Seminar held at the Armemuseum, Stockholm on the 26th - 27th of March 2009 showcased a range of activities supported by NKS over the previous 2 years and provided an opportunity to bring together researchers and end users from the wider NKS community. This summary seminar was the first joint venture between the NKS-R and NKS-B Programmes since the current two programme format was adopted by NKS. One of our intentions in organising the Joint Summary Seminar was to further the reciprocal awareness of ongoing research and issues under the respective NKS-R and NKS-B Programmes, with the aim of promoting new networking opportunities and generating new ideas and approaches to solving existing problems. (au)

International Aspects of Nuclear Safety

International Nuclear Information System (INIS)

Lash, T.R.

2000-01-01

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

Detecting communicative intent in a computerised test of joint attention

Directory of Open Access Journals (Sweden)

Nathan Caruana

2017-01-01

Full Text Available The successful navigation of social interactions depends on a range of cognitive faculties—including the ability to achieve joint attention with others to share information and experiences. We investigated the influence that intention monitoring processes have on gaze-following response times during joint attention. We employed a virtual reality task in which 16 healthy adults engaged in a collaborative game with a virtual partner to locate a target in a visual array. In the Search task, the virtual partner was programmed to engage in non-communicative gaze shifts in search of the target, establish eye contact, and then display a communicative gaze shift to guide the participant to the target. In the NoSearch task, the virtual partner simply established eye contact and then made a single communicative gaze shift towards the target (i.e., there were no non-communicative gaze shifts in search of the target. Thus, only the Search task required participants to monitor their partner’s communicative intent before responding to joint attention bids. We found that gaze following was significantly slower in the Search task than the NoSearch task. However, the same effect on response times was not observed when participants completed non-social control versions of the Search and NoSearch tasks, in which the avatar’s gaze was replaced by arrow cues. These data demonstrate that the intention monitoring processes involved in differentiating communicative and non-communicative gaze shifts during the Search task had a measurable influence on subsequent joint attention behaviour. The empirical and methodological implications of these findings for the fields of autism and social neuroscience will be discussed.

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition); Seguridad radiologica en la radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-12-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Is road safety management linked to road safety performance?

Science.gov (United States)

Papadimitriou, Eleonora; Yannis, George

2013-10-01

This research aims to explore the relationship between road safety management and road safety performance at country level. For that purpose, an appropriate theoretical framework is selected, namely the 'SUNflower' pyramid, which describes road safety management systems in terms of a five-level hierarchy: (i) structure and culture, (ii) programmes and measures, (iii) 'intermediate' outcomes'--safety performance indicators (SPIs), (iv) final outcomes--fatalities and injuries, and (v) social costs. For each layer of the pyramid, a composite indicator is implemented, on the basis of data for 30 European countries. Especially as regards road safety management indicators, these are estimated on the basis of Categorical Principal Component Analysis upon the responses of a dedicated road safety management questionnaire, jointly created and dispatched by the ETSC/PIN group and the 'DaCoTA' research project. Then, quasi-Poisson models and Beta regression models are developed for linking road safety management indicators and other indicators (i.e. background characteristics, SPIs) with road safety performance. In this context, different indicators of road safety performance are explored: mortality and fatality rates, percentage reduction in fatalities over a given period, a composite indicator of road safety final outcomes, and a composite indicator of 'intermediate' outcomes (SPIs). The results of the analyses suggest that road safety management can be described on the basis of three composite indicators: "vision and strategy", "budget, evaluation and reporting", and "measurement of road user attitudes and behaviours". Moreover, no direct statistical relationship could be established between road safety management indicators and final outcomes. However, a statistical relationship was found between road safety management and 'intermediate' outcomes, which were in turn found to affect 'final' outcomes, confirming the SUNflower approach on the consecutive effect of each layer

Health and usage monitoring system for the small aircraft composite structure

Science.gov (United States)

Růžička, Milan; Dvořák, Milan; Schmidová, Nikola; Šašek, Ladislav; Štěpánek, Martin

2017-07-01

This paper is focused on the design of the health and usage monitoring system (HUMS) of the composite ultra-light aircrafts. A multichannel measuring system was developed and installed for recording of the long-term operational measurements of the UL airplane. Many fiber Bragg grating sensors were implemented into the composite aircraft structure, mainly in the glue joints. More than ten other analog functions and signals of the aircraft is monitored and can be correlated together. Changing of the FBG sensors responses in monitored places and their correlations, comparing with the calibration and recalibration procedures during a monitored life may indicate damage (eg. in bonded joints) and complements the HUMS system.

49 CFR 385.107 - The safety audit.

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false The safety audit. 385.107 Section 385.107 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR CARRIER SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS SAFETY FITNESS PROCEDURES Safety Monitoring System for Mexico-Domicile...

Safety in cardiac surgery

NARCIS (Netherlands)

Siregar, S.

2013-01-01

The monitoring of safety in cardiac surgery is a complex process, which involves many clinical, practical, methodological and statistical issues. The objective of this thesis was to measure and to compare safety in cardiac surgery in The Netherlands using the Netherlands Association for

Research on Joint Parameter Inversion for an Integrated Underground Displacement 3D Measuring Sensor

Directory of Open Access Journals (Sweden)

Nanying Shentu

2015-04-01

Full Text Available Underground displacement monitoring is a key means to monitor and evaluate geological disasters and geotechnical projects. There exist few practical instruments able to monitor subsurface horizontal and vertical displacements simultaneously due to monitoring invisibility and complexity. A novel underground displacement 3D measuring sensor had been proposed in our previous studies, and great efforts have been taken in the basic theoretical research of underground displacement sensing and measuring characteristics by virtue of modeling, simulation and experiments. This paper presents an innovative underground displacement joint inversion method by mixing a specific forward modeling approach with an approximate optimization inversion procedure. It can realize a joint inversion of underground horizontal displacement and vertical displacement for the proposed 3D sensor. Comparative studies have been conducted between the measured and inversed parameters of underground horizontal and vertical displacements under a variety of experimental and inverse conditions. The results showed that when experimentally measured horizontal displacements and vertical displacements are both varied within 0 ~ 30 mm, horizontal displacement and vertical displacement inversion discrepancies are generally less than 3 mm and 1 mm, respectively, under three kinds of simulated underground displacement monitoring circumstances. This implies that our proposed underground displacement joint inversion method is robust and efficient to predict the measuring values of underground horizontal and vertical displacements for the proposed sensor.

Development of an above-knee prosthesis equipped with a microcomputer-controlled knee joint: first test results.

Science.gov (United States)

Aeyels, B; Peeraer, L; Vander Sloten, J; Van der Perre, G

1992-05-01

The shortcomings of conventional above-knee prostheses are due to their lack of adaptive control. Implementation of a microcomputer controlling the knee joint in a passive way has been suggested to enhance the patient's gait comfort, safety and cosmesis. This approach was used in the design of a new prosthetic system for the above-knee amputee, and tested on one patient. The knee joint of a conventional, modular prosthesis was replaced by a knee joint mechanism, equipped with a controllable brake on the knee joint axis. Sensors and a microcomputer were added, keeping the system self-contained. The modularity of the design permits the use of an alternative, external, PC-based control unit, emulating the self-contained one, and offering extended data monitoring and storage facilities. For both units an operating environment was written, including sensor/actuator interfacing and the implementation of a real-time interrupt, executing the control algorithm. A double finite state approach was used in the design of the control algorithm. On a higher level, the mode identification algorithm reveals the patient's intent. Within a specific mode (lower level), the relevant mode control algorithm looks for the current phase within the gait cycle. Within a particular phase, a specific simple control action with the brake replaces normal knee muscle activity. Tests were carried out with one prosthetic patient using a basic control algorithm for level walking, allowing controlled knee flexion during stance phase. The technical feasibility of such a concept is illustrated by the test results, even though only flexion during early stance phase was controlled during the trials.(ABSTRACT TRUNCATED AT 250 WORDS)

Estimation of RC slab-column joints effective strength using neural networks

Directory of Open Access Journals (Sweden)

A. A. Shah

Full Text Available The nominal strength of slab-column joints made of highstrength concrete (HSC columns and normal strength concrete (NSC slabs is of great importance in structural design and construction of concrete buildings. This topic has been intensively studied during the last decades. Different types of column-slab joints have been investigated experimentally providing a basis for developing design provisions. However, available data does not cover all classes of concretes, reinforcements, and possible loading cases for the proper calculation of joint stresses necessary for design purposes. New numerical methods based on modern software seem to be effective and may allow reliable prediction of column-slab joint strength. The current research is focused on analysis of available experimental data on different slab-to-column joints with the aim of predicting the nominal strength of slabcolumn joint. Neural networks technique is proposed herein using MATLAB routines developed to analyze available experimental data. The obtained results allow prediction of the effective strength of column-slab joints with accuracy and good correlation coefficients when compared to regression based models. The proposed method enables the user to predict the effective design of column-slab joints without the need for conservative safety coefficients generally promoted and used by most construction codes.

Automated radiological monitoring at a Russian Ministry of Defence Naval Site

International Nuclear Information System (INIS)

Moskowitz, P.D.; Pomerville, J.; Gavrilov, S.; Kisselev, V.; Daniylan, V.; Belikov, A.; Egorkin, A.; Sokolovski, Y.; Endregard, M.; Krosshavn, M.; Sundling, C.V.; Yokstad, H.

2001-01-01

The Arctic Military Environmental Cooperation (AMEC) Program is a cooperative effort between the military establishments of the Kingdom of Norway, the Russian Federation, and the US. This paper discusses joint activities conducted over the past year among Norwegian, Russian, and US technical experts on a project to develop, demonstrate and implement automated radiological monitoring at Russian Navy facilities engaged in the dismantlement of nuclear-powered strategic ballistic missile launching submarines. Radiological monitoring is needed at these facilities to help protect workers engaged in the dismantlement program and the public living within the footprint of routine and accidental radiation exposure areas. By providing remote stand-alone monitoring, the Russian Navy will achieve added protection due to the defense-in-depth strategy afforded by local (at the site), regional (Kola) and national-level (Moscow) oversight. The system being implemented at the Polyaminsky Russian Naval Shipyard was developed from a working model tested at the Russian Institute for Nuclear Safety, Moscow, Russia. It includes Russian manufactured terrestrial and underwater gamma detectors, smart controllers for graded sampling, radio-modems for offsite transmission of the data, and a data fusion/display system: The data fusion/display system is derived from the Norwegian Picasso AMEC Environmental Monitoring software package. This computer package allows monitoring personnel to review the real-time and historical status of monitoring at specific sites and objects and to establish new monitoring protocols as required, for example, in an off-normal accident situation. Plans are being developed to implement the use of this system at most RF Naval sites handling spent nuclear fuel

Locations of Joint Physical Activity in Parent-Child Pairs Based on Accelerometer and GPS Monitoring

Science.gov (United States)

Dunton, Genevieve Fridlund; Liao, Yue; Almanza, Estela; Jerrett, Micheal; Spruijt-Metz, Donna; Pentz, Mary Ann

2012-01-01

Background Parental factors may play an important role in influencing children’s physical activity levels. Purpose This cross-sectional study sought to describe the locations of joint physical activity among parents and children. Methods Parent-child pairs (N = 291) wore an Actigraph GT2M accelerometer and GlobalSat BT-335 Global Positioning Systems (GPS) device over the same 7-day period. Children were ages 8–14 years. Joint behavior was defined by a linear separation distance of less than 50m between parent and child. Land use classifications were assigned to GPS data points. Results Joint physical activity was spread across residential locations (35%), and commercial venues (24%), and open spaces/parks (20%). Obese children and parents performed less joint physical activity in open spaces/parks than under/normal weight children and parents (p’s parent-child physical activity naturally occurs may inform location-based interventions to promote these behaviors. PMID:23011914

White paper on nuclear safety in 2009

International Nuclear Information System (INIS)

2009-06-01

It deals with a general introduction of nuclear safety like general safety, safety regulation and system law and standard. It indicates of nuclear energy facility safety about general safety, safety regulation of operating nuclear power plant safety regulation under constructing nuclear power plant. It deals with radiation facility safety, monitoring of environmental radiation, radiation protection, radiation control, international cooperating on nuclear energy safety and establishment of safety regulation.

Application of a distributed optical fiber sensing technique in monitoring the stress of precast piles

International Nuclear Information System (INIS)

Lu, Y; Shi, B; Wei, G Q; Zhang, D; Chen, S E

2012-01-01

Due to its ability in providing long distance, distributed sensing, the optical fiber sensing technique based on a Brillouin optical time domain reflectometer (BOTDR) has a unique advantage in monitoring the stability and safety of linear structures. This paper describes the application of a BOTDR-based technique to measure the stress within precast piles. The principle behind the BOTDR and the embedding technique for the sensing optical fiber in precast piles is first introduced, and then the analysis method and deformation and stress calculation based on distributed strain data are given. Finally, a methodology for using a BOTDR-based monitoring workflow for in situ monitoring of precast piles, combined with a practical example, is introduced. The methodology requires implantation of optical fibers prior to pile placement. Field experimental results show that the optical fiber implantation method with slotting, embedding, pasting and jointing is feasible, and have accurately measured the axial force, side friction, end-bearing resistance and bearing feature of the precast pile according to the strain measuring data. (paper)

Integration of radiation protection in safety management: sharing best practices between radiation protection and other safety areas

International Nuclear Information System (INIS)

Kockerols, Pierre; Fessler, Andreas

2008-01-01

Full text: The Institute for Reference Materials and Measurements (IRMM) located in Geel is one of the seven institutes of the Joint Research Centre of the European Commission (EC, DG JRC). The institute was founded in 1960 as a nuclear research centre, but has gradually shifted its activities to also include 'non-nuclear' domains, mainly in the areas of food safety and environmental surveillance. As the activities on the IRMM site are currently quite diversified, they necessitate the operation of nuclear controlled areas, accelerators, as well as bio safety restricted areas and chemical laboratories. Therefore, the care for occupational health and safety and for environmental protection has to take into consideration various types of hazards and threats. Recently an integrated management system according to ISO-9001, ISO-14001 and OHSAS-18001 was implemented. The integrated system combines 'vertically' quality, occupational health and safety and environmental issues and covers 'horizontally' the nuclear, biological and chemical fields. The paper outlines how the radiation protection can be included in an overall health, safety and environmental management system. It will give various practical examples where synergies can be applied: 1-) the overall policy; 2-) The assessment and ranking of all risks and the identification, in a combined way, of the appropriate prevention measures; 3-) The planning and review of related actions; 4-) The monitoring, auditing and registration of anomalies and incidents and the definition of corrective actions; 5-) The training of personnel based on lessons learned from past experiences; 6-) The organisation of an internal emergency plan dealing with nuclear and non-nuclear hazards. Based on these examples, the benefits of having an integrated approach are commented. In addition, the paper will illustrate how the recent ICRP fundamental recommendations and more particularly some of the principles of radiation protection such as

Risk-based safety indicators

International Nuclear Information System (INIS)

Szikszai, T.

1997-01-01

The presentation discusses the following issues: The objectives of the risk-based indicator programme. The characteristics of the risk-based indicators. The objectives of risk-based safety indicators - in monitoring safety; in PSA applications. What indicators? How to produce the risk based indicators? PSA requirements

Applied Health Physics and Safety annual report for 1975

International Nuclear Information System (INIS)

1976-08-01

This report describes and summarizes the activities of the applied sections and/or groups of the Health Physics Division. Projects and activities covered include personnel monitoring, environmental monitoring, radiation and safety surveys, and industrial safety

Safety performance indicators used by the Russian Safety Regulatory Authority in its practical activities on nuclear power plant safety regulation

International Nuclear Information System (INIS)

Khazanov, A.L.

2005-01-01

The Sixth Department of the Nuclear, Industrial and Environmental Regulatory Authority of Russia, Scientific and Engineering Centre for Nuclear and Radiation Safety process, analyse and use the information on nuclear power plants (NPPs) operational experience or NPPs safety improvement. Safety performance indicators (SPIs), derived from processing of information on operational violations and analysis of annual NPP Safety Reports, are used as tools to determination of trends towards changing of characteristics of operational safety, to assess the effectiveness of corrective measures, to monitor and evaluate the current operational safety level of NPPs, to regulate NPP safety. This report includes a list of the basic SPIs, those used by the Russian safety regulatory authority in regulatory activity. Some of them are absent in list of IAEA-TECDOC-1141 ('Operational safety performance indicators for nuclear power plants'). (author)

Plantar impact causing midfoot fractures result in higher forces in Chopart's joint than in the ankle joint.

Science.gov (United States)

Richter, M; Wippermann, B; Thermann, H; Schroeder, G; Otte, D; Troeger, H D; Krettek, C

2002-03-01

Force effect (impact, extent of foot compartment deformation) and result (fracture pattern) for midfoot fractures in car occupants is known. An analysis of the processes in the foot was intended to improve car safety. Eleven fresh, unfrozen, unpreserved intact human cadavers (age: 36.8 (16-61) years, gender: male, race: Caucasian) were studied 24-72 h after death. In 3 cadavers (5 feet) the experimental design was established: entire cadaver fixed on a special tray in supine position, pendulum with bar impactor hitting the foot plantar to Lisfranc's joint. A custom-made pressure sensor was inserted in the ankle (A), talonavicular (TN) and calcaneocuboid (CC) joints (resolution: 1 cm2, sampling rate: 500/s). Sixteen feet were measured: midfoot fractures were induced in 11 feet. The maximum pressure amounted to 1.22-2.55 MPa (2.04+/-0.412) at 0.005 0.195 s (0.067+/-0.059) after impact. The maximum pressure occurred in 8 (50%) cases in the ankle, in 7 (44%) of the TN and 1 (6%) of the CC joints. A comparison of the first 200 pressure samples after impact of all sensor fields resulted in higher forces in Chopart's joint than in the ankle (t-test: p < 0.001). These force differences were higher in cases with midfoot fractures (mixed model analysis of variance: p = 0.003). Due to considerable forces in Chopart's joint we recommend a modification of the actual crash test dummy lower extremity model with an additional load cell that detects forces in the longitudinal direction of the foot axis.

Critical review of safety performance metrics

NARCIS (Netherlands)

Karanikas, Nektarios

2016-01-01

Various tools for safety performance measurement have been introduced in order to fulfil the need for safety monitoring in organisations, which is tightly related to their overall performance and achievement of their business goals. Such tools include accident rates, benchmarking, safety culture and