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Sample records for rapid automated nuclear

Rapid automated nuclear chemistry

International Nuclear Information System (INIS)

Meyer, R.A.

1979-01-01

Rapid Automated Nuclear Chemistry (RANC) can be thought of as the Z-separation of Neutron-rich Isotopes by Automated Methods. The range of RANC studies of fission and its products is large. In a sense, the studies can be categorized into various energy ranges from the highest where the fission process and particle emission are considered, to low energies where nuclear dynamics are being explored. This paper presents a table which gives examples of current research using RANC on fission and fission products. The remainder of this text is divided into three parts. The first contains a discussion of the chemical methods available for the fission product elements, the second describes the major techniques, and in the last section, examples of recent results are discussed as illustrations of the use of RANC
Automated rapid chemistry in heavy element research

International Nuclear Information System (INIS)

Schaedel, M.

1994-01-01

With the increasingly short half-lives of the heavy element isotopes in the transition region from the heaviest actinides to the transactinide elements the demand for automated rapid chemistry techniques is also increasing. Separation times of significantly less than one minute, high chemical yields, high repetition rates, and an adequate detection system are prerequisites for many successful experiments in this field. The development of techniques for separations in the gas phase and in the aqueous phase for applications of chemical or nuclear studies of the heaviest elements are briefly outlined. Typical examples of results obtained with automated techniques are presented for studies up to element 105, especially those obtained with the Automated Rapid Chemistry Apparatus, ARCA. The prospects to investigate the properties of even heavier elements with chemical techniques are discussed
RAPID AUTOMATED RADIOCHEMICAL ANALYZER FOR DETERMINATION OF TARGETED RADIONUCLIDES IN NUCLEAR PROCESS STREAMS

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Egorov, Oleg; Devol, Timothy A.

2008-01-01

Some industrial process-scale plants require the monitoring of specific radionuclides as an indication of the composition of their feed streams or as indicators of plant performance. In this process environment, radiochemical measurements must be fast, accurate, and reliable. Manual sampling, sample preparation, and analysis of process fluids are highly precise and accurate, but tend to be expensive and slow. Scientists at Pacific Northwest National Laboratory (PNNL) have assembled and characterized a fully automated prototype Process Monitor instrument which was originally designed to rapidly measure Tc-99 in the effluent streams of the Waste Treatment Plant at Hanford, WA. The system is capable of a variety of tasks: extraction of a precise volume of sample, sample digestion/analyte redox adjustment, column-based chemical separations, flow-through radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results can be immediately calculated and electronically reported. It is capable of performing a complete analytical cycle in less than 15 minutes. The system is highly modular and can be adapted to a variety of sample types and analytical requirements. It exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs
Automated nuclear materials accounting

International Nuclear Information System (INIS)

Pacak, P.; Moravec, J.

1982-01-01

An automated state system of accounting for nuclear materials data was established in Czechoslovakia in 1979. A file was compiled of 12 programs in the PL/1 language. The file is divided into four groups according to logical associations, namely programs for data input and checking, programs for handling the basic data file, programs for report outputs in the form of worksheets and magnetic tape records, and programs for book inventory listing, document inventory handling and materials balance listing. A similar automated system of nuclear fuel inventory for a light water reactor was introduced for internal purposes in the Institute of Nuclear Research (UJV). (H.S.)
Radioanalytical Chemistry for Automated Nuclear Waste Process Monitoring

International Nuclear Information System (INIS)

Egorov, Oleg B.; Grate, Jay W.; DeVol, Timothy A.

2003-01-01

This research program is directed toward rapid, sensitive, and selective determination of beta and alpha-emitting radionuclides such as 99Tc, 90Sr, and trans-uranium (TRU) elements in low activity waste (LAW) processing streams. The overall technical approach is based on automated radiochemical measurement principles. Nuclear waste process streams are particularly challenging for rapid analytical methods due to the complex, high- ionic-strength, caustic brine sample matrix, the presence of interfering radionuclides, and the variable and uncertain speciation of the radionuclides of interest. As a result, matrix modification, speciation control, and separation chemistries are required for use in automated process analyzers. Significant knowledge gaps exist relative to the design of chemistries for such analyzers so that radionuclides can be quantitatively and rapidly separated and analyzed in solutions derived from low-activity waste processing operations. This research is addressing these knowledge gaps in the area of separation science, nuclear detection, and analytical chemistry and instrumentation. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for sample matrix modification and analyte speciation control and chemistries for rapid and selective separation and preconcentration of target radionuclides from complex sample matrices. In addition, new approaches for quantification of alpha emitters in solution using solid state diode detectors, as well as improved instrumentation and signal processing techniques for use with solid-state and scintillation detectors, will be developed. New knowledge of the performance of separation materials, matrix modification and speciation control chemistries, instrument configurations, and quantitative analytical approaches will provide the basis for designing effective instrumentation for radioanalytical process monitoring. Specific analytical targets include 99 Tc, 90Sr and
Radioanalytical Chemistry for Automated Nuclear Waste Process Monitoring

International Nuclear Information System (INIS)

Egorov, Oleg B.; Grate, Jay W.; DeVol, Timothy A.

2004-01-01

This research program is directed toward rapid, sensitive, and selective determination of beta and alpha-emitting radionuclides such as 99Tc, 90Sr, and trans-uranium (TRU) elements in low activity waste (LAW) processing streams. The overall technical approach is based on automated radiochemical measurement principles, which entails integration of sample treatment and separation chemistries and radiometric detection within a single functional analytical instrument. Nuclear waste process streams are particularly challenging for rapid analytical methods due to the complex, high-ionic-strength, caustic brine sample matrix, the presence of interfering radionuclides, and the variable and uncertain speciation of the radionuclides of interest. As a result, matrix modification, speciation control, and separation chemistries are required for use in automated process analyzers. Significant knowledge gaps exist relative to the design of chemistries for such analyzers so that radionuclides can be quantitatively and rapidly separated and analyzed in solutions derived from low-activity waste processing operations. This research is addressing these knowledge gaps in the area of separation science, nuclear detection, and analytical chemistry and instrumentation. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for sample matrix modification and analyte speciation control and chemistries for rapid and selective separation and preconcentration of target radionuclides from complex sample matrices. In addition, new approaches for quantification of alpha emitters in solution using solid-state diode detectors, as well as improved instrumentation and signal processing techniques for use with solid-state and scintillation detectors, will be developed. New knowledge of the performance of separation materials, matrix modification and speciation control chemistries, instrument configurations, and quantitative analytical approaches will
Automated ultrasonic inspection of nuclear plant components

International Nuclear Information System (INIS)

Baron, J.A.; Dolbey, M.P.

1982-01-01

For reasons of safety and efficiency, automated systems are used in performing ultrasonic inspection of nuclear components. An automated system designed specifically for the inspection of headers in a nuclear plant is described. In-service inspection results obtained with this system are shown to correlate with pre-service inspection results obtained by manual methods
Rapid Automated Mission Planning System, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — The proposed innovation is an automated UAS mission planning system that will rapidly identify emergency (contingency) landing sites, manage contingency routing, and...
Nuclear power generation and automation technology

International Nuclear Information System (INIS)

Korei, Yoshiro

1985-01-01

The proportion of nuclear power in the total generated electric power has been increasing year after year, and the ensuring of its stable supply has been demanded. For the further development of nuclear power generation, the heightening of economical efficiency which is the largest merit of nuclear power and the public acceptance as a safe and stable electric power source are the important subjects. In order to solve these subjects, in nuclear power generation, various automation techniques have been applied for the purpose of the heightening of reliability, labor saving and the reduction of radiation exposure. Meeting the high needs of automation, the automation technology aided by computers have been applied to the design, manufacture and construction, operation and maintenance of nuclear power plants. Computer-aided design and the examples of design of a reactor building, pipings and a fuel assembly, an automatic welder for pipings of all position TIG welding type, a new central monitoring and control system, an automatic exchanger of control rod-driving mechanism, an automatic in-service inspection system for nozzles and pipings, and a robot for steam generator maintenance are shown. The trend of technical development and an intelligent moving robot, a system maintenance robot and a four legs walking robot are explained. (Kako, I.)
Automated rapid particle investigation using scanning electron microscopy

Science.gov (United States)

Wilkins, Jerod Laurence

The chemical composition of fly ash particles has been known to vary significantly depending on a number of factors. Current bulk methods of investigation including X-Ray Fluorescence and X-Ray Diffraction are thought to be inadequate in determining the performance of fly ash in concrete. It is the goal of this research to develop a method of Automated Rapid Particle Investigation that will not look at fly ash as a bulk material but as individual particles. By examining each particle individually scientists and engineers will have the ability to study the variation in chemical composition by comparing the chemistry present in each particle. The method of investigation developed by this research provides a practical technique that will allow the automated chemical analysis of hundreds, or even thousands, of fly ash particles in a matter of minutes upon completion of sample preparation and automated scanning electron microscope (ASEM) scanning. This research does not examine the significance of the chemical compounds discovered; rather, only the investigation methodology is discussed. Further research will be done to examine the importance of the chemistry discovered with this automated rapid particle investigation technique.
Automated processing of nuclear materials accounting data

International Nuclear Information System (INIS)

Straka, J.; Pacak, P.; Moravec, J.

1980-01-01

An automated system was developed of nuclear materials accounting in Czechoslovakia. The system allows automating data processing including data storage. It comprises keeping records of inventories and material balance. In designing the system, the aim of the IAEA was taken into consideration, ie., building a unified information system interconnected with state-run systems of accounting and checking nuclear materials in the signatory countries of the non-proliferation treaty. The nuclear materials accounting programs were written in PL-1 and were tested at an EC 1040 computer at UJV Rez where also the routine data processing takes place. (B.S.)
Complete automation of nuclear reactors control

International Nuclear Information System (INIS)

Weill, J.

1955-01-01

The use of nuclear reactor for energy production induces the installation of automatic control systems which need to be safe enough and can adapt to the industrial scale of energy production. These automatic control systems have to insure the constancy of power level and adjust the power produced to the energy demand. Two functioning modes are considered: nuclear plant connected up to other electric production systems as hydraulic or thermic plants or nuclear plants functioning on an independent network. For nuclear plants connected up with other production plants, xenon poisoning and operating cost lead to keep working at maximum power the nuclear reactors. Thus, the power modulation control system will not be considered and only start-up control, safety control, and control systems will be automated. For nuclear power plants working on an independent network, the power modulation control system is needed to economize fuel. It described the automated control system for reactors functioning with constant power: a power measurement system constituted of an ionization chamber and a direct-current amplifier will control the steadfastness of the power produced. For reactors functioning with variable power, the automated power control system will allow to change the power and maintain it steady with all the necessary safety and will control that working conditions under P max and R max (maximum power and maximum reactivity). The effects of temperature and xenon poisoning will also be discussed. Safety systems will be added to stop completely the functioning of the reactor if P max is reached. (M.P.)
Studies of works management and automation of nuclear power installations

International Nuclear Information System (INIS)

Besch, P.; Grossmann, J.; Hollasky, R.

1989-01-01

Erection and operation of nuclear power installations require investigations on their safety and availability. The works performed on the management of nuclear power plants and nuclear heating stations in the Working Group on Automation Engineering of the Dresden University of Technology are presented. Emphasis of the works is on simulation of dynamical performance of the plants and studies on the utilization of novel techniques concerning plant automation and process management. (author)
Determination of the Optimized Automation Rate considering Effects of Automation on Human Operators in Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Seung Min; Seong, Poong Hyun; Kim, Jong Hyun; Kim, Man Cheol

2015-01-01

Automation refers to the use of a device or a system to perform a function previously performed by a human operator. It is introduced to reduce the human errors and to enhance the performance in various industrial fields, including the nuclear industry. However, these positive effects are not always achieved in complex systems such as nuclear power plants (NPPs). An excessive introduction of automation can generate new roles for human operators and change activities in unexpected ways. As more automation systems are accepted, the ability of human operators to detect automation failures and resume manual control is diminished. This disadvantage of automation is called the Out-of-the- Loop (OOTL) problem. We should consider the positive and negative effects of automation at the same time to determine the appropriate level of the introduction of automation. Thus, in this paper, we suggest an estimation method to consider the positive and negative effects of automation at the same time to determine the appropriate introduction of automation. This concept is limited in that it does not consider the effects of automation on human operators. Thus, a new estimation method for automation rate was suggested to overcome this problem
Control and automation technology in United States nuclear power plants

International Nuclear Information System (INIS)

Sun, B.K.H.

1997-01-01

The need to use computers for nuclear power plant design, engineering, operation and maintenance has been growing since the inception of commercial nuclear power electricity generation in the 1960s. The needs have intensified in recent years as the demands of safety and reliability, as well as economic competition, have become stronger. The rapid advance of computer hardware and software technology in the last two decades has greatly enlarged the potential of computer applications to plant instrumentation and control of future plants, as well as those needed for operation of existing plants. The traditional role of computers for mathematical calculations and data manipulation has been expanded to automate plant control functions and to enhance human performance and productivity. The major goals of using computers for instrumentation and control of nuclear power plants are (1) to improve safety; (2) to reduce challenges to the power plant; (3) to reduce the cost of operations and maintenance; (4) to enhance power production, and (5) to increase productivity of people. Many functions in nuclear power plants are achieved by a combination of human action and automation. Increasingly, computer-based systems are used to support operations and maintenance personnel in the performance of their tasks. There are many benefits which can accrue from the use of computers but it is important to ensure that the design and implementation of the support system and the human task places the human in the correct role in relation to the machine; that is, in a management position, with the computer serving the human. In addition, consideration must be given to computer system integrity, software validation and verification, consequences of error, etc., to ensure its reliability for nuclear power plant applications. (author). 31 refs
Control and automation technology in United States nuclear power plants

International Nuclear Information System (INIS)

Sun, B.K.H.

1995-01-01

The need to use computers for nuclear power plant design, engineering, operation and maintenance has been growing since the inception of commercial nuclear power electricity generation in the 1960s. The needs have intensified in recent years as the demands of safety and reliability, as well as economic competition, have become stronger. The rapid advanced of computer hardware and software technology in the last two decades has greatly enlarged the potential of computer applications to plant instrumentation and control of future plants, as well as those needed for operation of existing plants. The traditional role of computers for mathematical calculations and data manipulation has been expanded to automate plant control functions and to enhance human performance and productivity. The major goals of using computers for instrumentation and control of nuclear power plants are: (1) to improve safety; (2) to reduce challenges to capital investments; (3) to reduce the cost of operations and maintenance; (4) to enhance power production; and (5) to increase productivity of people. Many functions in nuclear power plants are achieved by a combination of human action and automation. Increasingly, computer-based systems are used to support operations and maintenance personnel in the performance of their tasks. There are many benefits which can accrue from the use of computers but it is important to ensure that the design and implementation of the support system, and the human task places the human in the correct role in the relation to the machine; that is, in a management position, with the computer serving the human. In addition, consideration must be given to computer system integrity, software validation and verification, consequences of error, etc., to ensure its reliability for nuclear power plant applications. (author). 31 refs
Control and automation technology in United States nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Sun, B K.H. [Sunutech, Inc., Los Altos, CA (United States)

1997-07-01

The need to use computers for nuclear power plant design, engineering, operation and maintenance has been growing since the inception of commercial nuclear power electricity generation in the 1960s. The needs have intensified in recent years as the demands of safety and reliability, as well as economic competition, have become stronger. The rapid advance of computer hardware and software technology in the last two decades has greatly enlarged the potential of computer applications to plant instrumentation and control of future plants, as well as those needed for operation of existing plants. The traditional role of computers for mathematical calculations and data manipulation has been expanded to automate plant control functions and to enhance human performance and productivity. The major goals of using computers for instrumentation and control of nuclear power plants are (1) to improve safety; (2) to reduce challenges to the power plant; (3) to reduce the cost of operations and maintenance; (4) to enhance power production, and (5) to increase productivity of people. Many functions in nuclear power plants are achieved by a combination of human action and automation. Increasingly, computer-based systems are used to support operations and maintenance personnel in the performance of their tasks. There are many benefits which can accrue from the use of computers but it is important to ensure that the design and implementation of the support system and the human task places the human in the correct role in relation to the machine; that is, in a management position, with the computer serving the human. In addition, consideration must be given to computer system integrity, software validation and verification, consequences of error, etc., to ensure its reliability for nuclear power plant applications. (author). 31 refs.
Automations influence on nuclear power plants: a look at three accidents and how automation played a role.

Science.gov (United States)

Schmitt, Kara

2012-01-01

Nuclear power is one of the ways that we can design an efficient sustainable future. Automation is the primary system used to assist operators in the task of monitoring and controlling nuclear power plants (NPP). Automation performs tasks such as assessing the status of the plant's operations as well as making real time life critical situational specific decisions. While the advantages and disadvantages of automation are well studied in variety of domains, accidents remind us that there is still vulnerability to unknown variables. This paper will look at the effects of automation within three NPP accidents and incidents and will consider why automation failed in preventing these accidents from occurring. It will also review the accidents at the Three Mile Island, Chernobyl, and Fukushima Daiichi NPP's in order to determine where better use of automation could have resulted in a more desirable outcome.
Automated software analysis of nuclear core discharge data

International Nuclear Information System (INIS)

Larson, T.W.; Halbig, J.K.; Howell, J.A.; Eccleston, G.W.; Klosterbuer, S.F.

1993-03-01

Monitoring the fueling process of an on-load nuclear reactor is a full-time job for nuclear safeguarding agencies. Nuclear core discharge monitors (CDMS) can provide continuous, unattended recording of the reactor's fueling activity for later, qualitative review by a safeguards inspector. A quantitative analysis of this collected data could prove to be a great asset to inspectors because more information can be extracted from the data and the analysis time can be reduced considerably. This paper presents a prototype for an automated software analysis system capable of identifying when fuel bundle pushes occurred and monitoring the power level of the reactor. Neural network models were developed for calculating the region on the reactor face from which the fuel was discharged and predicting the burnup. These models were created and tested using actual data collected from a CDM system at an on-load reactor facility. Collectively, these automated quantitative analysis programs could help safeguarding agencies to gain a better perspective on the complete picture of the fueling activity of an on-load nuclear reactor. This type of system can provide a cost-effective solution for automated monitoring of on-load reactors significantly reducing time and effort
Sensors and Automated Analyzers for Radionuclides

International Nuclear Information System (INIS)

Grate, Jay W.; Egorov, Oleg B.

2003-01-01

The production of nuclear weapons materials has generated large quantities of nuclear waste and significant environmental contamination. We have developed new, rapid, automated methods for determination of radionuclides using sequential injection methodologies to automate extraction chromatographic separations, with on-line flow-through scintillation counting for real time detection. This work has progressed in two main areas: radionuclide sensors for water monitoring and automated radiochemical analyzers for monitoring nuclear waste processing operations. Radionuclide sensors have been developed that collect and concentrate radionuclides in preconcentrating minicolumns with dual functionality: chemical selectivity for radionuclide capture and scintillation for signal output. These sensors can detect pertechnetate to below regulatory levels and have been engineered into a prototype for field testing. A fully automated process monitor has been developed for total technetium in nuclear waste streams. This instrument performs sample acidification, speciation adjustment, separation and detection in fifteen minutes or less

Intelligent Automated Nuclear Fuel Pellet Inspection System

International Nuclear Information System (INIS)

Keyvan, S.

1999-01-01

At the present time, nuclear pellet inspection is performed manually using naked eyes for judgment and decisionmaking on accepting or rejecting pellets. This current practice of pellet inspection is tedious and subject to inconsistencies and error. Furthermore, unnecessary re-fabrication of pellets is costly and the presence of low quality pellets in a fuel assembly is unacceptable. To improve the quality control in nuclear fuel fabrication plants, an automated pellet inspection system based on advanced techniques is needed. Such a system addresses the following concerns of the current manual inspection method: (1) the reliability of inspection due to typical human errors, (2) radiation exposure to the workers, and (3) speed of inspection and its economical impact. The goal of this research is to develop an automated nuclear fuel pellet inspection system which is based on pellet video (photographic) images and uses artificial intelligence techniques
Status of automated nuclear scanning systems

International Nuclear Information System (INIS)

Gold, R.; Roberts, J.H.; Preston, C.C.; McNeece, J.P.; Ruddy, F.H.

1983-07-01

Present day minicomputers and microprocessors enable a range of automation, from partial to total, of tasks once thought beyond approach. The status of three computer controlled systems for quantitative track measurements is reviewed. Two systems, the Hanford optical track scanner (HOTS) and an automated scanning electron microscope (ASEM) are used for scanning solid state track recorders (SSTR). The third systems, the emulsion scanning processor (ESP), is an interactive system used to measure the length of proton tracks in nuclear research emulsions (NRE). Current limitations of these systems for quantitative track scanning are presented. Experimental uncertainties attained with these computer controlled systems are described using results obtained from reactor neutron dosimetry
Concept of a computer network architecture for complete automation of nuclear power plants

International Nuclear Information System (INIS)

Edwards, R.M.; Ray, A.

1990-01-01

The state of the art in automation of nuclear power plants has been largely limited to computerized data acquisition, monitoring, display, and recording of process signals. Complete automation of nuclear power plants, which would include plant operations, control, and management, fault diagnosis, and system reconfiguration with efficient and reliable man/machine interactions, has been projected as a realistic goal. This paper presents the concept of a computer network architecture that would use a high-speed optical data highway to integrate diverse, interacting, and spatially distributed functions that are essential for a fully automated nuclear power plant
Safety analysis code input automation using the Nuclear Plant Data Bank

International Nuclear Information System (INIS)

Kopp, H.; Leung, J.; Tajbakhsh, A.; Viles, F.

1985-01-01

The Nuclear Plant Data Bank (NPDB) is a computer-based system that organizes a nuclear power plant's technical data, providing mechanisms for data storage, retrieval, and computer-aided engineering analysis. It has the specific objective to describe thermohydraulic systems in order to support: rapid information retrieval and display, and thermohydraulic analysis modeling. The Nuclear Plant Data Bank (NPBD) system fully automates the storage and analysis based on this data. The system combines the benefits of a structured data base system and computer-aided modeling with links to large scale codes for engineering analysis. Emphasis on a friendly and very graphically oriented user interface facilitates both initial use and longer term efficiency. Specific features are: organization and storage of thermohydraulic data items, ease in locating specific data items, graphical and tabular display capabilities, interactive model construction, organization and display of model input parameters, input deck construction for TRAC and RELAP analysis programs, and traceability of plant data, user model assumptions, and codes used in the input deck construction process. The major accomplishments of this past year were the development of a RELAP model generation capability and the development of a CRAY version of the code
Development of an automated system of nuclear materials accounting for nuclear power stations with water-cooled, water-moderated reactors

International Nuclear Information System (INIS)

Babaev, N.S.

1981-06-01

The results of work carried out under IAEA Contract No. 2336/RB are described (subject: an automated system of nuclear materials accounting for nuclear power stations with water-cooled, water-moderated (VVER) reactors). The basic principles of an accounting system for this type of nuclear power plant are outlined. The general structure and individual units of the information computer program used to achieve automated accounting are described and instructions are given on the use of the program. A detailed example of its application (on a simulated nuclear power plant) is examined
Automated radioanalytical system incorporating microwave-assisted sample preparation, chemical separation, and online radiometric detection for the monitoring of total 99Tc in nuclear waste processing streams.

Science.gov (United States)

Egorov, Oleg B; O'Hara, Matthew J; Grate, Jay W

2012-04-03

An automated fluidic instrument is described that rapidly determines the total (99)Tc content of aged nuclear waste samples, where the matrix is chemically and radiologically complex and the existing speciation of the (99)Tc is variable. The monitor links microwave-assisted sample preparation with an automated anion exchange column separation and detection using a flow-through solid scintillator detector. The sample preparation steps acidify the sample, decompose organics, and convert all Tc species to the pertechnetate anion. The column-based anion exchange procedure separates the pertechnetate from the complex sample matrix, so that radiometric detection can provide accurate measurement of (99)Tc. We developed a preprogrammed spike addition procedure to automatically determine matrix-matched calibration. The overall measurement efficiency that is determined simultaneously provides a self-diagnostic parameter for the radiochemical separation and overall instrument function. Continuous, automated operation was demonstrated over the course of 54 h, which resulted in the analysis of 215 samples plus 54 hly spike-addition samples, with consistent overall measurement efficiency for the operation of the monitor. A sample can be processed and measured automatically in just 12.5 min with a detection limit of 23.5 Bq/mL of (99)Tc in low activity waste (0.495 mL sample volume), with better than 10% RSD precision at concentrations above the quantification limit. This rapid automated analysis method was developed to support nuclear waste processing operations planned for the Hanford nuclear site.
Conceptual designs of automated systems for underground emplacement and retrieval of nuclear waste

International Nuclear Information System (INIS)

Slocum, A.H.; Hou, W.M.; Park, K.; Hochmuth, C.; Thurston, D.C.

1987-01-01

Current designs of underground nuclear waste repositories have not adequately addressed the possibility of automated, unmanned emplacement and retrieval. This report will present design methodologies for development of an automated system for underground emplacement of nuclear waste. By scaling generic issues to different repositories, it is shown that a two vehicle automated waste emplacement/retrieval system can be designed to operate in a fail-safe mode. Evaluation of cost at this time is not possible. Significant gains in worker safety, however, can be realized by minimizing the possibility of human exposure
A sensor-based automation system for handling nuclear materials

International Nuclear Information System (INIS)

Drotning, W.; Kimberly, H.; Wapman, W.; Darras, D.

1997-01-01

An automated system is being developed for handling large payloads of radioactive nuclear materials in an analytical laboratory. The automation system performs unpacking and repacking of payloads from shipping and storage containers, and delivery of the payloads to the stations in the laboratory. The system uses machine vision and force/torque sensing to provide sensor-based control of the automation system in order to enhance system safety, flexibility, and robustness, and achieve easy remote operation. The automation system also controls the operation of the laboratory measurement systems and the coordination of them with the robotic system. Particular attention has been given to system design features and analytical methods that provide an enhanced level of operational safety. Independent mechanical gripper interlock and tool release mechanisms were designed to prevent payload mishandling. An extensive Failure Modes and Effects Analysis of the automation system was developed as a safety design analysis tool
On the automated assessment of nuclear reactor systems code accuracy

International Nuclear Information System (INIS)

Kunz, Robert F.; Kasmala, Gerald F.; Mahaffy, John H.; Murray, Christopher J.

2002-01-01

An automated code assessment program (ACAP) has been developed to provide quantitative comparisons between nuclear reactor systems (NRS) code results and experimental measurements. The tool provides a suite of metrics for quality of fit to specific data sets, and the means to produce one or more figures of merit (FOM) for a code, based on weighted averages of results from the batch execution of a large number of code-experiment and code-code data comparisons. Accordingly, this tool has the potential to significantly streamline the verification and validation (V and V) processes in NRS code development environments which are characterized by rapidly evolving software, many contributing developers and a large and growing body of validation data. In this paper, a survey of data conditioning and analysis techniques is summarized which focuses on their relevance to NRS code accuracy assessment. A number of methods are considered for their applicability to the automated assessment of the accuracy of NRS code simulations. A variety of data types and computational modeling methods are considered from a spectrum of mathematical and engineering disciplines. The goal of the survey was to identify needs, issues and techniques to be considered in the development of an automated code assessment procedure, to be used in United States Nuclear Regulatory Commission (NRC) advanced thermal-hydraulic T/H code consolidation efforts. The ACAP software was designed based in large measure on the findings of this survey. An overview of this tool is summarized and several NRS data applications are provided. The paper is organized as follows: The motivation for this work is first provided by background discussion that summarizes the relevance of this subject matter to the nuclear reactor industry. Next, the spectrum of NRS data types are classified into categories, in order to provide a basis for assessing individual comparison methods. Then, a summary of the survey is provided, where each
Automated control system for the Temelin nuclear power plant

International Nuclear Information System (INIS)

Labik, V.

1990-01-01

Instrumentation of the automated control system of the Temelin nuclear power plant in the section of the main production unit and of the major auxiliary equipment is described, the results of testing are reported, and the present status of design activities is assessed. The suitability of application of Czechoslovak automation facilities to the instrumentation of the automated control system of the power plant was confirmed by the Soviet designer and supplier based on favorable results of polygonal testing. Capacity problems in the development of the designs and user software are alleviated by extensive cooperation. It is envisaged that all tasks will be fulfilled as planned. (P.A.). 1 fig., 5 refs
Improving automated load flexibility of nuclear power plants with ALFC

Energy Technology Data Exchange (ETDEWEB)

Kuhn, Andreas [AREVA GmbH, Karlstein (Germany). Plant Control/Training; Klaus, Peter [E.ON NPP Isar 2, Essenbach (Germany). Plant Operation/Production Engineering

2016-07-01

In several German and Swiss Nuclear Power Plants with Pressurized Water Reactor (PWR) the control of the reactor power was and will be improved in order to be able to support the energy transition with increasing volatile renewable energy in the grid by flexible load operation according to the need of the load dispatcher (power system stability). Especially regarding the mentioned German NPPs with a nominal electric power of approx. 1,500 MW, the general objectives are the main automated grid relevant operation modes. The new possibilities of digital I and C (as TELEPERM {sup registered} XS) enable the automation of the operating modes provided that manual support is no longer necessary. These possibilities were and will be implemented by AREVA within the ALFC-projects. Manifold adaption algorithms to the reactor physical variations during the nuclear load cycle enable a precise control of the axial power density distribution and of the reactivity management in the reactor core. Finally this is the basis for a highly automated load flexibility with the parallel respect and surveillance of the operational limits of a PWR.
Improving automated load flexibility of nuclear power plants with ALFC

Energy Technology Data Exchange (ETDEWEB)

Kuhn, Andreas [AREVA GmbH, Karlstein (Germany). Section Manager Training; Klaus, Peter [Preussenelektra NPP, Essenbach (Germany). Production Engineering

2017-03-15

In several German and Swiss Nuclear Power Plants with Pressurized Water Reactor (PWR) the control of the reactor power was and will be improved in order to be able to support the energy transition with increasing volatile renewable energy in the grid by flexible load operation according to the need of the load dispatcher (power system stability). Especially regarding the mentioned German NPPs with a nominal electric power of approx. 1500 MW, the general objectives are several automated grid relevant operation modes. The new possibilities of digital I and C (as TELEPERM {sup registered} XS) enable the automation of this operating modes provided that manual support is no longer necessary. These possibilities were and will be implemented by AREVA within the ALFC-projects. Manifold adaption algorithms to the reactor physical variations during the nuclear load cycle enable a precise control of the axial power density distribution and of the reactivity manage - ment in the reactor core. Finally this is the basis for a highly automated load flexibility with the parallel respect and surveillance of the operational limits of a PWR.
Automated system for processing nuclear emulsion data on nuclear-nuclear interactions for EMU-15 CERN experiment

International Nuclear Information System (INIS)

Aleksandrov, A.B.; Azarenkova, I.Yu.; Feinberg, E.L.; Goneharova, L.A.; Martynov, A.G.; Polukhina, N.G.; Starkov, N.I.

2004-01-01

The EMU-15 experiment has been performed at CERN by the LPI group with the aim of studying characteristics of high-density and high-temperature nuclear matter, in particular, for searching for manifestation of quark-gluon plasma. The main problem inherent in these investigations is a large amount of track measurements in nuclear emulsions. A very efficient Completely Automated Measuring Complex (Russian abbreviation sounds as P AVICOM ) for track-detector data processing in nuclear and high-energy particle physics is operating at the Lebedev Physical Institute. The PAVICOM provides essential improving the efficiency of experimental studies performed not only by the LPI group, but also by many Russian Institutes
Optimization of automation: III. Development of optimization method for determining automation rate in nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Min; Kim, Jong Hyun; Kim, Man Cheol; Seong, Poong Hyun

2016-01-01

Highlights: • We propose an appropriate automation rate that enables the best human performance. • We analyze the shortest working time considering Situation Awareness Recovery (SAR). • The optimized automation rate is estimated by integrating the automation and ostracism rate estimation methods. • The process to derive the optimized automation rate is demonstrated through case studies. - Abstract: Automation has been introduced in various industries, including the nuclear field, because it is commonly believed that automation promises greater efficiency, lower workloads, and fewer operator errors through reducing operator errors and enhancing operator and system performance. However, the excessive introduction of automation has deteriorated operator performance due to the side effects of automation, which are referred to as Out-of-the-Loop (OOTL), and this is critical issue that must be resolved. Thus, in order to determine the optimal level of automation introduction that assures the best human operator performance, a quantitative method of optimizing the automation is proposed in this paper. In order to propose the optimization method for determining appropriate automation levels that enable the best human performance, the automation rate and ostracism rate, which are estimation methods that quantitatively analyze the positive and negative effects of automation, respectively, are integrated. The integration was conducted in order to derive the shortest working time through considering the concept of situation awareness recovery (SAR), which states that the automation rate with the shortest working time assures the best human performance. The process to derive the optimized automation rate is demonstrated through an emergency operation scenario-based case study. In this case study, four types of procedures are assumed through redesigning the original emergency operating procedure according to the introduced automation and ostracism levels. Using the
Automated personal identification: a new technique for controlling access to nuclear materials and facilities

International Nuclear Information System (INIS)

Eccles, D.R.

1975-01-01

Special nuclear materials must be protected against the threat of diversion or theft, and nuclear facilities against the threat of industrial sabotage. Implicit in this protection is the means of controlling access to protected areas, material access areas, and vital areas. With the advent of automated personal identification technology, the processes of access control can be automated to yield both higher security and reduced costs. This paper first surveys the conventional methods of access control; next, automated personal identification concepts are presented and various systems approaches are highlighted; finally, Calspan's FINGERSCAN /sub TM/ system for identity verification is described
About the automated instrumentation in nuclear power plants; Sobre la instrumentacion automatizada en plantas nucleares

Energy Technology Data Exchange (ETDEWEB)

Segovia de los Rios, J. A.; Benitez R, J. S. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Garduno G, M P., E-mail: armando.segovia@inin.gob.mx [Instituto Tecnologica de Toluca, Av. Tecnologico s/n, 52140 Metepec, Estado de Mexico (Mexico)

2011-11-15

The automation of the inspection processes and monitoring in nuclear facilities have as main objective the reduction of acquired radiation dose for the operators of the diverse work programs. For example, a typical maintenance task is the problems correction of leaks in the hydraulic facilities of the vapor circuits where is necessary the repair of pipes, measuring and control elements, as the valves. A program of effective maintenance should contemplate strategies of appropriate monitoring for the immediate detection of possible failures, with the purpose of the remedy them opportunely. For this function of failures detection is necessary to have instruments that allow the measuring of the parameters that facilitate their characterization. Given the prevailing conditions in the nuclear facilities, such instruments should possess special characteristics, reason why is necessary a study of them, as well as a careful selection of the susceptible apparatuses of being used. For this reason, this work presents a discussion about some of the existent conditions in the nuclear power plants, as well as the aspects to consider for the automated instrumentation of some places of a nuclear power plant. (Author)
Operating procedure automation to enhance safety of nuclear power plants

International Nuclear Information System (INIS)

Husseiny, A.A.; Sabri, Z.A.; Adams, S.K.; Rodriguez, R.J.; Packer, D.; Holmes, J.W.

1989-01-01

Use of logic statements and computer assist are explored as means for automation and improvement on design of operating procedures including those employed in abnormal and emergency situations. Operating procedures for downpower and loss of forced circulation are used for demonstration. Human-factors analysis is performed on generic emergency operating procedures for three strategies of control; manual, semi-automatic and automatic, using standard emergency operating procedures. Such preliminary analysis shows that automation of procedures is feasible provided that fault-tolerant software and hardware become available for design of the controllers. Recommendations are provided for tests to substantiate the promise of enhancement of plant safety. Adequate design of operating procedures through automation may alleviate several major operational problems of nuclear power plants. Also, automation of procedures is necessary for partial or overall automatic control of plants. Fully automatic operations are needed for space applications while supervised automation of land-based and offshore plants may become the thrust of new generation of nulcear power plants. (orig.)
Use of automation and mechanization elements in welding and surfacing nuclear reactor pressure vessels

International Nuclear Information System (INIS)

Bartak, J.; Elckner, J.

1986-01-01

The problems are discussed of automation and mechanization of individual operations in the production cycle of pressure vessels whose manufacture cannot for its great exactingness be automated as a whole. Examples are given of workplaces and single-purpose welding facilities with a high level of automation. The present state of the development and implementation of automation of arc welding is described and further development is indicated of the automation of welding processes in the manufacture of nuclear facilities. (J.C.)
Optimization of automation: I. Estimation method of cognitive automation rates reflecting the effects of automation on human operators in nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Min; Kim, Jong Hyun; Seong, Poong Hyun

2014-01-01

Highlights: • We propose an estimation method of the automation rate by taking the advantages of automation as the estimation measures. • We conduct the experiments to examine the validity of the suggested method. • The higher the cognitive automation rate is, the greater the decreased rate of the working time will be. • The usefulness of the suggested estimation method is proved by statistical analyses. - Abstract: Since automation was introduced in various industrial fields, the concept of the automation rate has been used to indicate the inclusion proportion of automation among all work processes or facilities. Expressions of the inclusion proportion of automation are predictable, as is the ability to express the degree of the enhancement of human performance. However, many researchers have found that a high automation rate does not guarantee high performance. Therefore, to reflect the effects of automation on human performance, this paper proposes a new estimation method of the automation rate that considers the effects of automation on human operators in nuclear power plants (NPPs). Automation in NPPs can be divided into two types: system automation and cognitive automation. Some general descriptions and characteristics of each type of automation are provided, and the advantages of automation are investigated. The advantages of each type of automation are used as measures of the estimation method of the automation rate. One advantage was found to be a reduction in the number of tasks, and another was a reduction in human cognitive task loads. The system and the cognitive automation rate were proposed as quantitative measures by taking advantage of the aforementioned benefits. To quantify the required human cognitive task loads and thus suggest the cognitive automation rate, Conant’s information-theory-based model was applied. The validity of the suggested method, especially as regards the cognitive automation rate, was proven by conducting
Concept of automated system for spent fuel utilization ('Reburning') from compact nuclear reactors

International Nuclear Information System (INIS)

Ianovski, V.V.; Lozhkin, O.V.; Nesterov, M.M.; Tarasov, N.A.; Uvarov, V.I.

1997-01-01

On the basic concept of an automated system of nuclear power installation safety is developed the utilization project of spent fuel from compact nuclear reactors. The main features of this project are: 1. design and creation of the mobile model-industrial installation; 2. development of the utilization and storage diagram of the spent fuel from compact nuclear reactors, with the specific recommendation for the natatorial means using both for the nuclear fuel reburning, for its transportation in places of the storage; 3. research of an opportunity during the utilization process to obtain additional power resources, ozone and others to increase of justifying expenses at the utilization; 4. creation of new generation engineering for the automation of remote control processes in the high radiation background conditions. 7 refs., 1 fig

Rapid and Automated Determination of Plutonium and Neptunium in Environmental Samples

DEFF Research Database (Denmark)

Qiao, Jixin

This thesis presents improved analytical methods for rapid and automated determination of plutonium and neptunium in environmental samples using sequential injection (SI) based chromatography and inductively coupled plasma mass spectrometry (ICP-MS). The progress of methodology development...... and optimization for rapid determination of plutonium in environmental samples using SIextraction chromatography prior to inductively coupled plasma mass spectrometry (Paper III); (3) Development of an SI-chromatographic method for simultaneous determination of plutonium and neptunium in environmental samples...... for rapid and simultaneous determination of plutonium and neptunium within an SI system (Paper VI). The results demonstrate that the developed methods in this study are reliable and efficient for accurate assays of trace levels of plutonium and neptunium as demanded in different situations including...
Balance between automation and human actions in nuclear power plant operation. Results of international cooperation

International Nuclear Information System (INIS)

Sun, B.; Olmstead, R.; Oudiz, A.; Jenkinson, J.; Kossilov, A.

1990-01-01

Automation has long been an established feature of power plants. In some applications, the use of automation has been the significant factor which has enabled plant technology to progress to its current state. Societal demands for increased levels of safety have led to greater use of redundancy and diversity and this, in turn, has increased levels of automation. However, possibly the greatest contributory factor in increased automation has resulted from improvements in information technology. Much recent attention has been focused on the concept of inherently safe reactors, which may simplify safety system requirements and information and control system complexity. The allocation of tasks between man and machine may be one of the most critical activity in the design of new nuclear plants and major retro-fits and it therefore warrants a design approach which is commensurate in quality with the high levels of safety and production performance sought from nuclear plants. Facing this climate, in 1989 the International Atomic Energy Agency (IAEA) formed an advisory group from member countries with extensive experience in nuclear power plant automation. The task of this group was to advise on the appropriate balance between manual and automatic actions in plant operation
Balance between automation and human actions in nuclear power plant operation. Results of international cooperation

International Nuclear Information System (INIS)

Sun, B.; Olmstead, R.; Oudiz, A.; Jenkinson, J.; Kossilov, A.

1990-01-01

Automation has long been an established feature of power plants. In some applications, the use of automation has been the significant factor which has enabled plant technology to progress to its current state. Societal demands for increased levels of safety have led to greater use of redundancy and diversity and this, in turn, has increased levels of automation. However, possibly the greatest contributory factor in increased automation has resulted from improvements in information technology. Much recent attention has been focused on the concept of inherently safe reactors, which may simplify safety system requirements and information and control system complexity. The allocation of tasks between man and machine may be one of the most critical activity in the design of new nuclear plants and major retro-fits and it therefore warrants a design approach which is commensurate in quality with the high levels of safety and production performance sought from nuclear plants. Facing this climate, in 1989 the International Atomic Energy Agency (IAEA) formed an advisory group from member countries with extensive experience in nuclear power plant automation. The task of this group was to advise on the appropriate balance between manual and automatic actions in plant operation. (author) [fr
Automating Hyperspectral Data for Rapid Response in Volcanic Emergencies

Science.gov (United States)

Davies, Ashley G.; Doubleday, Joshua R.; Chien, Steve A.

2013-01-01

In a volcanic emergency, time is of the essence. It is vital to quantify eruption parameters (thermal emission, effusion rate, location of activity) and distribute this information as quickly as possible to decision-makers in order to enable effective evaluation of eruption-related risk and hazard. The goal of this work was to automate and streamline processing of spacecraft hyperspectral data, automate product generation, and automate distribution of products. Visible and Short-Wave Infrared Images of volcanic eruption in Iceland in May 2010." class="caption" align="right">The software rapidly processes hyperspectral data, correcting for incident sunlight where necessary, and atmospheric transmission; detects thermally anomalous pixels; fits data with model black-body thermal emission spectra to determine radiant flux; calculates atmospheric convection thermal removal; and then calculates total heat loss. From these results, an estimation of effusion rate is made. Maps are generated of thermal emission and location (see figure). Products are posted online, and relevant parties notified. Effusion rate data are added to historical record and plotted to identify spikes in activity for persistently active eruptions. The entire process from start to end is autonomous. Future spacecraft, especially those in deep space, can react to detection of transient processes without the need to communicate with Earth, thus increasing science return. Terrestrially, this removes the need for human intervention.
Weld controller for automated nuclear service welding

International Nuclear Information System (INIS)

Barfield, K.L.; Strubhar, P.M.; Green, D.I.

1995-01-01

B and W Nuclear Technologies (BWNT) uses many different types of weld heads for automated welding in the commercial nuclear service industry. Some weld heads are purchased as standard items, while others are custom designed and fabricated by BWNT requiring synchronized multiaxis motion control. BWNT recently completed a development program to build a common weld controller that interfaces to all types of weld heads used by BWNT. Their goal was to construct a system that had the flexibility to add different modules to increase the capability of the controller as different application needs become necessary. The benefits from having a common controller are listed. This presentation explains the weld controller system and the types of applications to which it has been applied
Sensors and Automated Analyzers for Radionuclides

International Nuclear Information System (INIS)

Grate, Jay W.; Egorov, Oleg B.; O'Hara, Matthew J.

2005-01-01

The production of nuclear weapons materials has generated a legacy of nuclear waste and contaminated environmental sites. (1) The remediation of radiochemically contaminated sites and processing of stored wastes into stable waste forms will require characterization procedures throughout all phases of these activities. (2) Consequently the demands for radiochemical analysis will increase rapidly in the future. Methods are required to do these analyses rapidly and precisely. To meet these characterization needs, new automated techniques are required in order to provide improved precision, consistent analytical protocols, reduced worker exposure to toxic and/or radioactive samples, greater sample throughput, reduced costs, and reduced secondary waste generation. Furthermore, methods are required that provide automatic analyses in settings other than analytical laboratories
Operator-based metric for nuclear operations automation assessment

Energy Technology Data Exchange (ETDEWEB)

Zacharias, G.L.; Miao, A.X.; Kalkan, A. [Charles River Analytics Inc., Cambridge, MA (United States)] [and others

1995-04-01

Continuing advances in real-time computational capabilities will support enhanced levels of smart automation and AI-based decision-aiding systems in the nuclear power plant (NPP) control room of the future. To support development of these aids, we describe in this paper a research tool, and more specifically, a quantitative metric, to assess the impact of proposed automation/aiding concepts in a manner that can account for a number of interlinked factors in the control room environment. In particular, we describe a cognitive operator/plant model that serves as a framework for integrating the operator`s information-processing capabilities with his procedural knowledge, to provide insight as to how situations are assessed by the operator, decisions made, procedures executed, and communications conducted. Our focus is on the situation assessment (SA) behavior of the operator, the development of a quantitative metric reflecting overall operator awareness, and the use of this metric in evaluating automation/aiding options. We describe the results of a model-based simulation of a selected emergency scenario, and metric-based evaluation of a range of contemplated NPP control room automation/aiding options. The results demonstrate the feasibility of model-based analysis of contemplated control room enhancements, and highlight the need for empirical validation.
Intelligent control and automation technology for nuclear application

International Nuclear Information System (INIS)

Kim, Jae Hee; Eom, Heung Sub; Kim, Ko Ryu; Lee, Jae Cheol; Choi, You Rak; Lee, Soo Cheol

1996-06-01

Using recent technologies on a mobile robot and computer science, we developed an automatic inspection system for weld lines of the reactor pressure vessel. The ultrasonic inspection of the reactor pressure vessel is currently performed by commercialized robot manipulators. Since, however, the conventional fixed type robot manipulator is very huge, heavy and expensive, it needs long inspection time and is hard to handle and maintain. In order to resolve these problems, we developed a new inspection automation system using a small mobile robot crawling on the vertical wall. According to the conceptual design studied in the first year, we developed the inspection automation system including an underwater inspection robot, a laser position control subsystem and a main control subsystem. And we carried out underwater experiments on the reactor vessel mockup. After finishing this project successfully, we have a plan to commercialize our inspection system. Using this system, we can expect much reduction of the inspection time, performance enhancement, automatic management of inspection history, etc. In the economic point of view, we can also expect import substitution more than 5 million dollars. The established essential technologies for intelligent control and automation are expected to be synthetically applied to the automation of similar systems in nuclear power plants. 4 tabs., 37 figs., 6 refs. (Author)
Development of Process Automation in the Neutron Activation Analysis Facility in Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Yussup, N.; Azman, A.; Ibrahim, M.M.; Rahman, N.A.A.; Che Sohashaari, S.; Atan, M.N.; Hamzah, M.A.; Mokhtar, M.; Khalid, M.A.; Salim, N.A.A.; Hamzah, M.S.

2018-01-01

Neutron Activation Analysis (NAA) has been established in Malaysian Nuclear Agency (Nuclear Malaysia) since 1980s. Most of the procedures established from sample registration to analysis are performed manually. These manual procedures carried out by the NAA laboratory personnel are time consuming and inefficient. Hence, system automation is developed in order to provide an effective method to replace redundant manual data entries and produce faster sample analysis and calculation process. This report explains NAA process in Nuclear Malaysia and describes the automation development in detail which includes sample registration software, automatic sample changer system which consists of hardware and software; and sample analysis software. (author)
Robotic and nuclear safety for an automated/teleoperated glove box system

International Nuclear Information System (INIS)

Domning, E.E.; McMahon, T.T.; Sievers, R.H.

1991-09-01

Lawrence Livermore National Laboratory (LLNL) is developing a fully automated system to handle the processing of special nuclear materials (SNM). This work is performed in response to the new goals at the Department of Energy (DOE) for hazardous waste minimization and radiation dose reduction. This fully automated system, called the automated test bed (ATB), consists of an IBM gantry robot and automated processing equipment sealed within a glove box. While the ATB is a cold system, we are designing it as a prototype of the future hot system. We recognized that identification and application of safety requirements early in the design phase will lead to timely installation and approval of the hot system. This paper identifies these safety issues as well as the general safety requirements necessary for the safe operation of the ATB. 4 refs., 2 figs
Development of An Optimization Method for Determining Automation Rate in Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Seung Min; Seong, Poong Hyun; Kim, Jong Hyun

2014-01-01

Since automation was introduced in various industrial fields, it has been known that automation provides positive effects like greater efficiency and fewer human errors, and negative effect defined as out-of-the-loop (OOTL). Thus, before introducing automation in nuclear field, the estimation of the positive and negative effects of automation on human operators should be conducted. In this paper, by focusing on CPS, the optimization method to find an appropriate proportion of automation is suggested by integrating the suggested cognitive automation rate and the concepts of the level of ostracism. The cognitive automation rate estimation method was suggested to express the reduced amount of human cognitive loads, and the level of ostracism was suggested to express the difficulty in obtaining information from the automation system and increased uncertainty of human operators' diagnosis. The maximized proportion of automation that maintains the high level of attention for monitoring the situation is derived by an experiment, and the automation rate is estimated by the suggested automation rate estimation method. It is expected to derive an appropriate inclusion proportion of the automation system avoiding the OOTL problem and having maximum efficacy at the same time
Development of nuclear power plant automated remote patrol system

International Nuclear Information System (INIS)

Nakayama, R.; Kubo, K.; Sato, K.; Taguchi, J.

1984-01-01

An Automated Remote Patrol System was developed for a remote inspection, observation and monitoring of nuclear power plant's components. This automated remote patrol system consists of; a vehicle moving along a monorail; three rails mounted in a monorail for data transmission and for power supply; an image fiber connected to a TV camera; an arm type mechanism (manipulator) for moving image fiber; a computer for control and data processing and operator's console. Special features of this Automated Remote Patrol System are as follows: The inspection vehicle runs along horizontal and vertical (up/down) monorails. The arm type mechanism (manipulator) on the vehicle is used to move image fiber. Slide type electric collectors are used for data transmission and power supply. Time-division multiplexing is adapted for data transmission. Voice communication is used for controlling mechanisms. Pattern recognition is used for data processing. The experience that has been obtained from a series of various tests is summarized. (author)
Innovative automation solutions applied to nuclear fuel production and inspection processes

International Nuclear Information System (INIS)

Vas, Ananth

2012-01-01

The nuclear industry in India is slated for fast paced growth in the coming years, with a great focus on increasing the capacity for producing, inspecting and finally reprocessing of nuclear fuel. Modern techniques of industrial automation such as robotics, machine vision and laser based systems have been deployed extensively to improve the productivity and output of existing and future installations, particularly for the fuel handling stages mentioned
Advances toward fully automated in vivo assessment of oral epithelial dysplasia by nuclear endomicroscopy-A pilot study.

Science.gov (United States)

Liese, Jan; Winter, Karsten; Glass, Änne; Bertolini, Julia; Kämmerer, Peer Wolfgang; Frerich, Bernhard; Schiefke, Ingolf; Remmerbach, Torsten W

2017-11-01

Uncertainties in detection of oral epithelial dysplasia (OED) frequently result from sampling error especially in inflammatory oral lesions. Endomicroscopy allows non-invasive, "en face" imaging of upper oral epithelium, but parameters of OED are unknown. Mucosal nuclei were imaged in 34 toluidine blue-stained oral lesions with a commercial endomicroscopy. Histopathological diagnosis showed four biopsies in "dys-/neoplastic," 23 in "inflammatory," and seven in "others" disease groups. Strength of different assessment strategies of nuclear scoring, nuclear count, and automated nuclear analysis were measured by area under ROC curve (AUC) to identify histopathological "dys-/neoplastic" group. Nuclear objects from automated image analysis were visually corrected. Best-performing parameters of nuclear-to-image ratios were the count of large nuclei (AUC=0.986) and 6-nearest neighborhood relation (AUC=0.896), and best parameters of nuclear polymorphism were the count of atypical nuclei (AUC=0.996) and compactness of nuclei (AUC=0.922). Excluding low-grade OED, nuclear scoring and count reached 100% sensitivity and 98% specificity for detection of dys-/neoplastic lesions. In automated analysis, combination of parameters enhanced diagnostic strength. Sensitivity of 100% and specificity of 87% were seen for distances of 6-nearest neighbors and aspect ratios even in uncorrected objects. Correction improved measures of nuclear polymorphism only. The hue of background color was stronger than nuclear density (AUC=0.779 vs 0.687) to detect dys-/neoplastic group indicating that macroscopic aspect is biased. Nuclear-to-image ratios are applicable for automated optical in vivo diagnostics for oral potentially malignant disorders. Nuclear endomicroscopy may promote non-invasive, early detection of dys-/neoplastic lesions by reducing sampling error. © 2017 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.
Complete automation of nuclear reactors control; Automatisation complete de la conduite des reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Weill, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

The use of nuclear reactor for energy production induces the installation of automatic control systems which need to be safe enough and can adapt to the industrial scale of energy production. These automatic control systems have to insure the constancy of power level and adjust the power produced to the energy demand. Two functioning modes are considered: nuclear plant connected up to other electric production systems as hydraulic or thermic plants or nuclear plants functioning on an independent network. For nuclear plants connected up with other production plants, xenon poisoning and operating cost lead to keep working at maximum power the nuclear reactors. Thus, the power modulation control system will not be considered and only start-up control, safety control, and control systems will be automated. For nuclear power plants working on an independent network, the power modulation control system is needed to economize fuel. It described the automated control system for reactors functioning with constant power: a power measurement system constituted of an ionization chamber and a direct-current amplifier will control the steadfastness of the power produced. For reactors functioning with variable power, the automated power control system will allow to change the power and maintain it steady with all the necessary safety and will control that working conditions under P{sub max} and R{sub max} (maximum power and maximum reactivity). The effects of temperature and xenon poisoning will also be discussed. Safety systems will be added to stop completely the functioning of the reactor if P{sub max} is reached. (M.P.)
Rapid, automated mosaicking of the human corneal subbasal nerve plexus.

Science.gov (United States)

Vaishnav, Yash J; Rucker, Stuart A; Saharia, Keshav; McNamara, Nancy A

2017-11-27

Corneal confocal microscopy (CCM) is an in vivo technique used to study corneal nerve morphology. The largest proportion of nerves innervating the cornea lie within the subbasal nerve plexus, where their morphology is altered by refractive surgery, diabetes and dry eye. The main limitations to clinical use of CCM as a diagnostic tool are the small field of view of CCM images and the lengthy time needed to quantify nerves in collected images. Here, we present a novel, rapid, fully automated technique to mosaic individual CCM images into wide-field maps of corneal nerves. We implemented an OpenCV image stitcher that accounts for corneal deformation and uses feature detection to stitch CCM images into a montage. The method takes 3-5 min to process and stitch 40-100 frames on an Amazon EC2 Micro instance. The speed, automation and ease of use conferred by this technique is the first step toward point of care evaluation of wide-field subbasal plexus (SBP) maps in a clinical setting.
Raexplore: Enabling Rapid, Automated Architecture Exploration for Full Applications

Energy Technology Data Exchange (ETDEWEB)

Zhang, Yao [Argonne National Lab. (ANL), Argonne, IL (United States); Balaprakash, Prasanna [Argonne National Lab. (ANL), Argonne, IL (United States); Meng, Jiayuan [Argonne National Lab. (ANL), Argonne, IL (United States); Morozov, Vitali [Argonne National Lab. (ANL), Argonne, IL (United States); Parker, Scott [Argonne National Lab. (ANL), Argonne, IL (United States); Kumaran, Kalyan [Argonne National Lab. (ANL), Argonne, IL (United States)

2014-12-01

We present Raexplore, a performance modeling framework for architecture exploration. Raexplore enables rapid, automated, and systematic search of architecture design space by combining hardware counter-based performance characterization and analytical performance modeling. We demonstrate Raexplore for two recent manycore processors IBM Blue- Gene/Q compute chip and Intel Xeon Phi, targeting a set of scientific applications. Our framework is able to capture complex interactions between architectural components including instruction pipeline, cache, and memory, and to achieve a 3–22% error for same-architecture and cross-architecture performance predictions. Furthermore, we apply our framework to assess the two processors, and discover and evaluate a list of architectural scaling options for future processor designs.
Development of a framework of human-centered automation for the nuclear industry

International Nuclear Information System (INIS)

Nelson, W.R.; Haney, L.N.

1993-01-01

Introduction of automated systems into control rooms for advanced reactor designs is often justified on the basis of increased efficiency and reliability, without a detailed assessment of how the new technologies will influence the role of the operator. Such a ''technology-centered'' approach carries with it the risk that entirely new mechanisms for human error will be introduced, resulting in some unpleasant surprises when the plant goes into operation. The aviation industry has experienced some of these surprises since the introduction of automated systems into the cockpits of advanced technology aircraft. Pilot errors have actually been induced by automated systems, especially when the pilot doesn't fully understand what the automated systems are doing during all modes of operation. In order to structure the research program for investigating these problems, the National Aeronautics and Space Administration (NASA) has developed a framework for human-centered automation. This framework is described in the NASA document Human-Centered Aircraft Automation Philosophy by Charles Billings. It is the thesis of this paper that a corresponding framework of human-centered automation should be developed for the nuclear industry. Such a framework would serve to guide the design and regulation of automated systems for advanced reactor designs, and would help prevent some of the problems that have arisen in other applications that have followed a ''technology-centered'' approach
Optical Coherence Tomography in the UK Biobank Study - Rapid Automated Analysis of Retinal Thickness for Large Population-Based Studies.

Directory of Open Access Journals (Sweden)

Pearse A Keane

Full Text Available To describe an approach to the use of optical coherence tomography (OCT imaging in large, population-based studies, including methods for OCT image acquisition, storage, and the remote, rapid, automated analysis of retinal thickness.In UK Biobank, OCT images were acquired between 2009 and 2010 using a commercially available "spectral domain" OCT device (3D OCT-1000, Topcon. Images were obtained using a raster scan protocol, 6 mm x 6 mm in area, and consisting of 128 B-scans. OCT image sets were stored on UK Biobank servers in a central repository, adjacent to high performance computers. Rapid, automated analysis of retinal thickness was performed using custom image segmentation software developed by the Topcon Advanced Biomedical Imaging Laboratory (TABIL. This software employs dual-scale gradient information to allow for automated segmentation of nine intraretinal boundaries in a rapid fashion.67,321 participants (134,642 eyes in UK Biobank underwent OCT imaging of both eyes as part of the ocular module. 134,611 images were successfully processed with 31 images failing segmentation analysis due to corrupted OCT files or withdrawal of subject consent for UKBB study participation. Average time taken to call up an image from the database and complete segmentation analysis was approximately 120 seconds per data set per login, and analysis of the entire dataset was completed in approximately 28 days.We report an approach to the rapid, automated measurement of retinal thickness from nearly 140,000 OCT image sets from the UK Biobank. In the near future, these measurements will be publically available for utilization by researchers around the world, and thus for correlation with the wealth of other data collected in UK Biobank. The automated analysis approaches we describe may be of utility for future large population-based epidemiological studies, clinical trials, and screening programs that employ OCT imaging.
Microwave-Assisted Sample Treatment in a Fully Automated Flow-Based Instrument: Oxidation of Reduced Technetium Species in the Analysis of Total Technetium-99 in Caustic Aged Nuclear Waste Samples

International Nuclear Information System (INIS)

Egorov, Oleg B.; O'Hara, Matthew J.; Grate, Jay W.

2004-01-01

An automated flow-based instrument for microwave-assisted treatment of liquid samples has been developed and characterized. The instrument utilizes a flow-through reaction vessel design that facilitates the addition of multiple reagents during sample treatment, removal of the gaseous reaction products, and enables quantitative removal of liquids from the reaction vessel for carryover-free operations. Matrix modification and speciation control chemistries that are required for the radiochemical determination of total 99Tc in caustic aged nuclear waste samples have been investigated. A rapid and quantitative oxidation procedure using peroxydisulfate in acidic solution was developed to convert reduced technetium species to pertechnetate in samples with high content of reducing organics. The effectiveness of the automated sample treatment procedures has been validated in the radiochemical analysis of total 99Tc in caustic aged nuclear waste matrixes from the Hanford site

Automated Radioanalytical Chemistry: Applications For The Laboratory And Industrial Process Monitoring

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Farawila, Anne F.; Grate, Jay W.

2009-01-01

The identification and quantification of targeted α- and β-emitting radionuclides via destructive analysis in complex radioactive liquid matrices is highly challenging. Analyses are typically accomplished at on- or off-site laboratories through laborious sample preparation steps and extensive chemical separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, alpha energy spectroscopy, mass spectrometry). Analytical results may take days or weeks to report. When an industrial-scale plant requires periodic or continuous monitoring of radionuclides as an indication of the composition of its feed stream, diversion of safeguarded nuclides, or of plant operational conditions (for example), radiochemical measurements should be rapid, but not at the expense of precision and accuracy. Scientists at Pacific Northwest National Laboratory have developed and characterized a host of automated radioanalytical systems designed to perform reproducible and rapid radioanalytical processes. Platforms have been assembled for (1) automation and acceleration of sample analysis in the laboratory and (2) automated monitors for monitoring industrial scale nuclear processes on-line with near-real time results. These methods have been applied to the analysis of environmental-level actinides and fission products to high-level nuclear process fluids. Systems have been designed to integrate a number of discrete sample handling steps, including sample pretreatment (e.g., digestion and valence state adjustment) and chemical separations. The systems have either utilized on-line analyte detection or have collected the purified analyte fractions for off-line measurement applications. One PNNL system of particular note is a fully automated prototype on-line radioanalytical system designed for the Waste Treatment Plant at Hanford, WA, USA. This system demonstrated nearly continuous destructive analysis of the soft β-emitting radionuclide 99Tc in nuclear
An automated robotic platform for rapid profiling oligosaccharide analysis of monoclonal antibodies directly from cell culture.

Science.gov (United States)

Doherty, Margaret; Bones, Jonathan; McLoughlin, Niaobh; Telford, Jayne E; Harmon, Bryan; DeFelippis, Michael R; Rudd, Pauline M

2013-11-01

Oligosaccharides attached to Asn297 in each of the CH2 domains of monoclonal antibodies play an important role in antibody effector functions by modulating the affinity of interaction with Fc receptors displayed on cells of the innate immune system. Rapid, detailed, and quantitative N-glycan analysis is required at all stages of bioprocess development to ensure the safety and efficacy of the therapeutic. The high sample numbers generated during quality by design (QbD) and process analytical technology (PAT) create a demand for high-performance, high-throughput analytical technologies for comprehensive oligosaccharide analysis. We have developed an automated 96-well plate-based sample preparation platform for high-throughput N-glycan analysis using a liquid handling robotic system. Complete process automation includes monoclonal antibody (mAb) purification directly from bioreactor media, glycan release, fluorescent labeling, purification, and subsequent ultra-performance liquid chromatography (UPLC) analysis. The entire sample preparation and commencement of analysis is achieved within a 5-h timeframe. The automated sample preparation platform can easily be interfaced with other downstream analytical technologies, including mass spectrometry (MS) and capillary electrophoresis (CE), for rapid characterization of oligosaccharides present on therapeutic antibodies. Copyright © 2013 Elsevier Inc. All rights reserved.
An Intelligent Automation Platform for Rapid Bioprocess Design.

Science.gov (United States)

Wu, Tianyi; Zhou, Yuhong

2014-08-01

Bioprocess development is very labor intensive, requiring many experiments to characterize each unit operation in the process sequence to achieve product safety and process efficiency. Recent advances in microscale biochemical engineering have led to automated experimentation. A process design workflow is implemented sequentially in which (1) a liquid-handling system performs high-throughput wet lab experiments, (2) standalone analysis devices detect the data, and (3) specific software is used for data analysis and experiment design given the user's inputs. We report an intelligent automation platform that integrates these three activities to enhance the efficiency of such a workflow. A multiagent intelligent architecture has been developed incorporating agent communication to perform the tasks automatically. The key contribution of this work is the automation of data analysis and experiment design and also the ability to generate scripts to run the experiments automatically, allowing the elimination of human involvement. A first-generation prototype has been established and demonstrated through lysozyme precipitation process design. All procedures in the case study have been fully automated through an intelligent automation platform. The realization of automated data analysis and experiment design, and automated script programming for experimental procedures has the potential to increase lab productivity. © 2013 Society for Laboratory Automation and Screening.
Automation, robotics and remote handling technology in the nuclear fuel cycle

International Nuclear Information System (INIS)

Rajagopalan, C.; Venugopal, S.

2013-01-01

Automation and Robotics technology are making significant contributions in almost all fields of engineering and technology and their presence is felt in all spheres of human life. The importance of automation and robotics has increased rapidly in the recent years to cater to the global competitive pressures by the manufacturing industry by utilizing the increased productivity and improved quality this technology offers. Improvement of productivity, quality, profitability and, indeed, survival are the major motivating factors in the implementation of automation and robotics technology in the manufacturing sector. Robots are used extensively in the automotive industry, primarily for welding, painting and material handling applications. The electronics, aerospace, metalworking and consumer goods industries are also major potential robot users. The common uses of robots in industries mostly include the four Ps - Picking, Placing, Packaging and Painting - apart from other industrial routines like assembly and welding. As is the case with industrial tools and machineries, a properly designed robot (for the appropriate task) has almost unlimited endurance with the added benefit of precisions unmatched by human workers. With robot technology as a key element, integrated factory automation systems touch on nearly all types of manufacturing. The productivity and competitiveness in these industries will depend in large part on flexible automation through robotics
Rapid and automated determination of plutonium and neptunium in environmental samples

International Nuclear Information System (INIS)

Qiao, J.

2011-03-01

This thesis presents improved analytical methods for rapid and automated determination of plutonium and neptunium in environmental samples using sequential injection (SI) based chromatography and inductively coupled plasma mass spectrometry (ICP-MS). The progress of methodology development in this work consists of 5 subjects stated as follows: 1) Development and optimization of an SI-anion exchange chromatographic method for rapid determination of plutonium in environmental samples in combination of inductively coupled plasma mass spectrometry detection (Paper II); (2) Methodology development and optimization for rapid determination of plutonium in environmental samples using SI-extraction chromatography prior to inductively coupled plasma mass spectrometry (Paper III); (3) Development of an SI-chromatographic method for simultaneous determination of plutonium and neptunium in environmental samples (Paper IV); (4) Investigation of the suitability and applicability of 242 Pu as a tracer for rapid neptunium determination using anion exchange chromatography in an SI-network coupled with inductively coupled plasma mass spectrometry (Paper V); (5) Exploration of macro-porous anion exchange chromatography for rapid and simultaneous determination of plutonium and neptunium within an SI system (Paper VI). The results demonstrate that the developed methods in this study are reliable and efficient for accurate assays of trace levels of plutonium and neptunium as demanded in different situations including environmental risk monitoring and assessment, emergency preparedness and surveillance of contaminated areas. (Author)
Rapid and automated determination of plutonium and neptunium in environmental samples

Energy Technology Data Exchange (ETDEWEB)

Qiao, J.

2011-03-15

This thesis presents improved analytical methods for rapid and automated determination of plutonium and neptunium in environmental samples using sequential injection (SI) based chromatography and inductively coupled plasma mass spectrometry (ICP-MS). The progress of methodology development in this work consists of 5 subjects stated as follows: 1) Development and optimization of an SI-anion exchange chromatographic method for rapid determination of plutonium in environmental samples in combination of inductively coupled plasma mass spectrometry detection (Paper II); (2) Methodology development and optimization for rapid determination of plutonium in environmental samples using SI-extraction chromatography prior to inductively coupled plasma mass spectrometry (Paper III); (3) Development of an SI-chromatographic method for simultaneous determination of plutonium and neptunium in environmental samples (Paper IV); (4) Investigation of the suitability and applicability of 242Pu as a tracer for rapid neptunium determination using anion exchange chromatography in an SI-network coupled with inductively coupled plasma mass spectrometry (Paper V); (5) Exploration of macro-porous anion exchange chromatography for rapid and simultaneous determination of plutonium and neptunium within an SI system (Paper VI). The results demonstrate that the developed methods in this study are reliable and efficient for accurate assays of trace levels of plutonium and neptunium as demanded in different situations including environmental risk monitoring and assessment, emergency preparedness and surveillance of contaminated areas. (Author)
Automated rapid method for the determination of Ni-63 in deconstruction of nuclear facilities- and environmental samples; Automatisiertes Schnellverfahren zur Bestimmung von Ni-63 in Rueckbau- und Umweltproben

Energy Technology Data Exchange (ETDEWEB)

Bach, M.; Flucht, R.; Burow, M.; Zoriy, M.V. [Forschungszentrum Juelich GmbH, Juelich (Germany)

2012-07-01

Because of the increasing demand on the deconstruction of nuclear facilities in the last few years, a rapid method for the determination of Ni-63 in environmental samples is required. At Juelich, Division of Safety and Radiation Protection we have established a routine method, based on the determination of Ni-63 in the environmental samples using extraction chromatography separation from 2000[1] and optimize the sample preparation. Samples of different matrices were prepared by wet chemical methods for the extraction chromatography separation. For the separation the samples were introduced manually via a peristaltic pump or by using developed automated separation system equipped with the extraction chromatography column of Ni-Resin. Nickel[2] forms a Dimethylglyoximkomplex (DMG) and can be separated. The activity of the Ni-63 then were measured bei means of liquid scintillation counter (LSC), the recovery was determined using MC-ICP-MS. The yields of the Ni-carrier for the develped procure was higher than 90% with the accuracy below 10%. The developed method allows the relatively simple and fast determination of Ni-63 in environmental samples with a detection limit of 0.1 Bq/l. (orig.)
Robotic control architecture development for automated nuclear material handling systems

International Nuclear Information System (INIS)

Merrill, R.D.; Hurd, R.; Couture, S.; Wilhelmsen, K.

1995-02-01

Lawrence Livermore National Laboratory (LLNL) is engaged in developing automated systems for handling materials for mixed waste treatment, nuclear pyrochemical processing, and weapon components disassembly. In support of these application areas there is an extensive robotic development program. This paper will describe the portion of this effort at LLNL devoted to control system architecture development, and review two applications currently being implemented which incorporate these technologies
A Continuous Automated Vault Inventory System (CAVIS) for accountability monitoring of stored nuclear materials

International Nuclear Information System (INIS)

Pickett, C.A.; Barham, M.A.; Gafford, T.A.; Hutchinson, D.P.; Jordan, J.K.; Maxey, L.C.; Moran, B.W.; Muhs, J.; Nodine, R.; Simpson, M.L.

1994-01-01

Nearly all facilities that store hazardous (radioactive or non-radioactive) materials must comply with prevailing federal, state, and local laws. These laws usually have components that require periodic physical inspections to insure that all materials remain safely and securely stored. The inspections are generally labor intensive, slow, put personnel at risk, and only find anomalies after they have occurred. The system described in this paper was developed for monitoring stored nuclear materials resulting from weapons dismantlement, but its applications extend to any storage facility that meets the above criteria. The traditional special nuclear material (SNM) accountability programs, that are currently used within most of the Department of Energy (DOE) complex, require the physical entry of highly trained personnel into SNM storage vaults. This imposes the need for additional security measures, which typically mandate that extra security personnel be present while SNM inventories are performed. These requirements increase labor costs and put additional personnel at risk to radiation exposure. In some cases, individuals have received radiation exposure equivalent to the annual maximum during just one inventory verification. With increasing overhead costs, the current system is rapidly becoming too expensive to operate, the need for an automated method of inventory verification is evident. The Continuous Automated Vault Inventory System (CAVIS) described in this paper was designed and prototyped as a low cost, highly reliable, and user friendly system that is capable of providing, real-time weight, gamma. and neutron energy confirmation from each item stored in a SNM vault. This paper describes the sensor technologies, the CAVIS prototype system (built at Y- 12 for highly enriched uranium storage), the technical requirements that must be achieved to assure successful implementation, and descriptions of sensor technologies needed for a plutonium facility
A Continuous Automated Vault Inventory System (CAVIS) for accountability monitoring of stored nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Pickett, C.A.; Barham, M.A.; Gafford, T.A.; Hutchinson, D.P.; Jordan, J.K.; Maxey, L.C.; Moran, B.W.; Muhs, J.; Nodine, R.; Simpson, M.L. [and others

1994-12-08

Nearly all facilities that store hazardous (radioactive or non-radioactive) materials must comply with prevailing federal, state, and local laws. These laws usually have components that require periodic physical inspections to insure that all materials remain safely and securely stored. The inspections are generally labor intensive, slow, put personnel at risk, and only find anomalies after they have occurred. The system described in this paper was developed for monitoring stored nuclear materials resulting from weapons dismantlement, but its applications extend to any storage facility that meets the above criteria. The traditional special nuclear material (SNM) accountability programs, that are currently used within most of the Department of Energy (DOE) complex, require the physical entry of highly trained personnel into SNM storage vaults. This imposes the need for additional security measures, which typically mandate that extra security personnel be present while SNM inventories are performed. These requirements increase labor costs and put additional personnel at risk to radiation exposure. In some cases, individuals have received radiation exposure equivalent to the annual maximum during just one inventory verification. With increasing overhead costs, the current system is rapidly becoming too expensive to operate, the need for an automated method of inventory verification is evident. The Continuous Automated Vault Inventory System (CAVIS) described in this paper was designed and prototyped as a low cost, highly reliable, and user friendly system that is capable of providing, real-time weight, gamma. and neutron energy confirmation from each item stored in a SNM vault. This paper describes the sensor technologies, the CAVIS prototype system (built at Y- 12 for highly enriched uranium storage), the technical requirements that must be achieved to assure successful implementation, and descriptions of sensor technologies needed for a plutonium facility.
A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I)

International Nuclear Information System (INIS)

Kim, W.

1985-01-01

The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during perceives and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant * General Requirement. * Principle and Methods of Ultrasonic Test. * Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspire of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huge system, the
Alternate ways for automation of evaluating nuclear physical data reliability from primary literature

International Nuclear Information System (INIS)

Golashvili, T.V.; Tsvetaev, S.M.

1983-01-01

Methods, possible ways, criteria and algorithms for organizing an automated system for evaluating nuclear physical data reliability from primary literature are discussed. It is noted that automation of data reliability evaluation does not substitute for a scientist dealing with data evaluation. It only releases him from hard, monotonous and tedious work not requiring erudition or profound knowledge. Computers will facilitate and accelerate the work of the expert and, hence, leat to a sharp increase of a bulk of works on evaluation of data reliability
An Intelligent Automation Platform for Rapid Bioprocess Design

Science.gov (United States)

Wu, Tianyi

2014-01-01

Bioprocess development is very labor intensive, requiring many experiments to characterize each unit operation in the process sequence to achieve product safety and process efficiency. Recent advances in microscale biochemical engineering have led to automated experimentation. A process design workflow is implemented sequentially in which (1) a liquid-handling system performs high-throughput wet lab experiments, (2) standalone analysis devices detect the data, and (3) specific software is used for data analysis and experiment design given the user’s inputs. We report an intelligent automation platform that integrates these three activities to enhance the efficiency of such a workflow. A multiagent intelligent architecture has been developed incorporating agent communication to perform the tasks automatically. The key contribution of this work is the automation of data analysis and experiment design and also the ability to generate scripts to run the experiments automatically, allowing the elimination of human involvement. A first-generation prototype has been established and demonstrated through lysozyme precipitation process design. All procedures in the case study have been fully automated through an intelligent automation platform. The realization of automated data analysis and experiment design, and automated script programming for experimental procedures has the potential to increase lab productivity. PMID:24088579
ETRAN 1999: Society for Electronics,Telecommunications, Computers, Automation and Nuclear Engineering. Section for Nuclear Techniques and Technology. Proceedings of the XLIII Conference. Vol IV

International Nuclear Information System (INIS)

Spasojevic, D.; Smiljanic, M.; Bozic, D.; Stankovic, D.

1999-01-01

The XLIII ETRAN Conference of the Society for Electronic, Telecommunications, Computers, Automation and Nuclear Engineering was held on 20-22 Sep, 1999. In the Proceedings of the Conference The Commission of the Nuclear Technique and Technology has 19 papers presented in three sessions.
A utilization of fuzzy control for design automation of nuclear structures

International Nuclear Information System (INIS)

Yoshimura, Shinobu; Yagawa, Genki; Mochizuki, Yoshihiko

1991-01-01

This paper describes an automated design of nuclear structures by means of some artificial intelligence techniques. The 'generate and test' strategy is adopted as a basic strategy of design. An empirical approach with the fuzzy control is introduced for efficient design modification. This system is applied to the design of some 2D models of the fusion first wall. (author)
XVI International symposium on nuclear electronics and VI International school on automation and computing in nuclear physics and astrophysics

International Nuclear Information System (INIS)

Churin, I.N.

1995-01-01

Reports and papers of the 16- International Symposium on nuclear electronics and the 6- International school on automation and computing in nuclear physics and astrophysics are presented. The latest achievements in the field of development of fact - response electronic circuits designed for detecting and spectrometric facilities are studied. The peculiar attention is paid to the systems for acquisition, processing and storage of experimental data. The modern equipment designed for data communication in the computer networks is studied
The RABiT: a rapid automated biodosimetry tool for radiological triage. II. Technological developments.

Science.gov (United States)

Garty, Guy; Chen, Youhua; Turner, Helen C; Zhang, Jian; Lyulko, Oleksandra V; Bertucci, Antonella; Xu, Yanping; Wang, Hongliang; Simaan, Nabil; Randers-Pehrson, Gerhard; Lawrence Yao, Y; Brenner, David J

2011-08-01

Over the past five years the Center for Minimally Invasive Radiation Biodosimetry at Columbia University has developed the Rapid Automated Biodosimetry Tool (RABiT), a completely automated, ultra-high throughput biodosimetry workstation. This paper describes recent upgrades and reliability testing of the RABiT. The RABiT analyses fingerstick-derived blood samples to estimate past radiation exposure or to identify individuals exposed above or below a cut-off dose. Through automated robotics, lymphocytes are extracted from fingerstick blood samples into filter-bottomed multi-well plates. Depending on the time since exposure, the RABiT scores either micronuclei or phosphorylation of the histone H2AX, in an automated robotic system, using filter-bottomed multi-well plates. Following lymphocyte culturing, fixation and staining, the filter bottoms are removed from the multi-well plates and sealed prior to automated high-speed imaging. Image analysis is performed online using dedicated image processing hardware. Both the sealed filters and the images are archived. We have developed a new robotic system for lymphocyte processing, making use of an upgraded laser power and parallel processing of four capillaries at once. This system has allowed acceleration of lymphocyte isolation, the main bottleneck of the RABiT operation, from 12 to 2 sec/sample. Reliability tests have been performed on all robotic subsystems. Parallel handling of multiple samples through the use of dedicated, purpose-built, robotics and high speed imaging allows analysis of up to 30,000 samples per day.
ETRAN 2002: Society for Electronics,Telecommunications, Computers, Automation and Nuclear Engineering. Section for Nuclear Techniques and Technology. Proceedings of the XLVI Conference. Vol IV

International Nuclear Information System (INIS)

Milosevic, M.; Jaksic, Z.; Bozic, D.; Potkonjak, V.

2002-01-01

The XLVI ETRAN Conference of the Society for Electronic, Telecommunications, Computers, Automation and Nuclear Engineering was held on 4-7 June, 2002. In the Proceedings of the Conference The Commission of the Nuclear Technique and Technology has 14 papers presented in three following sessions: 1. Actual problems in nuclear technologies; 2. Accelerator and reactor systems; and 3. Radiation protection and ionizing radiation uses
RAPID-L Highly Automated Fast Reactor Concept Without Any Control Rods (1) Reactor concept and plant dynamics analyses

International Nuclear Information System (INIS)

Kambe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Iwamura, Takamichi

2002-01-01

The 200 kWe uranium-nitride fueled lithium cooled fast reactor concept 'RAPID-L' to achieve highly automated reactor operation has been demonstrated. RAPID-L is designed for Lunar base power system. It is one of the variants of RAPID (Refueling by All Pins Integrated Design), fast reactor concept, which enable quick and simplified refueling. The essential feature of RAPID concept is that the reactor core consists of an integrated fuel assembly instead of conventional fuel subassemblies. In this small size reactor core, 2700 fuel pins are integrated altogether and encased in a fuel cartridge. Refueling is conducted by replacing a fuel cartridge. The reactor can be operated without refueling for up to 10 years. Unique challenges in reactivity control systems design have been attempted in RAPID-L concept. The reactor has no control rod, but involves the following innovative reactivity control systems: Lithium Expansion Modules (LEM) for inherent reactivity feedback, Lithium Injection Modules (LIM) for inherent ultimate shutdown, and Lithium Release Modules (LRM) for automated reactor startup. All these systems adopt lithium-6 as a liquid poison instead of B 4 C rods. In combination with LEMs, LIMs and LRMs, RAPID-L can be operated without operator. This is the first reactor concept ever established in the world. This reactor concept is also applicable to the terrestrial fast reactors. In this paper, RAPID-L reactor concept and its transient characteristics are presented. (authors)
Research plan on programmable automation systems in nuclear power plants (OHA) in 1995-1998

International Nuclear Information System (INIS)

Haapanen, P.; Pulkkinen, U.; Korhonen, J.

1995-05-01

The main purpose of nuclear energy research is to ensure the safety and continued development of Finnish nuclear power plants - a task which places high demands on expertise needed to support the work of public authorities and power companies. A factor necessarily influencing the orientation of the research is the Parliament's decision of late 1993 against further nuclear capacity in the country. Therefore the main emphasis of research shall be directed towards the ensuring the safety of existing plants and the continuous development of their safety along the progress of the science and technology. Anyhow, the preparedness for constructing new plants shall also be preserved. The utilization of programmable digital automation technology for the safety critical functions is the most significant change in the new plants, but also in existing plants this technology will be used for replacing and complementing the ageing automation systems. The safety evaluation of programmable digital systems can not be based on methods applied to conventional analog systems but new evaluation methods and tools must be developed for the assessing of their acceptability. (5 refs., 1 fig., 2 tabs.)

Detection of cut-off point for rapid automized naming test in good readers and dyslexics

Directory of Open Access Journals (Sweden)

Zahra Soleymani

2014-01-01

Full Text Available Background and Aim: Rapid automized naming test is an appropriate tool to diagnose learning disability even before teaching reading. This study aimed to detect the cut-off point of this test for good readers and dyslexics.Methods: The test has 4 parts including: objects, colors, numbers and letters. 5 items are repeated on cards randomly for 10 times. Children were asked to name items rapidly. We studied 18 dyslexic students and 18 age-matched good readers between 7 and 8 years of age at second and third grades of elementary school; they were recruited by non-randomize sampling into 2 groups: children with developmental dyslexia from learning disabilities centers with mean age of 100 months, and normal children with mean age of 107 months from general schools in Tehran. Good readers selected from the same class of dyslexics.Results: The area under the receiver operating characteristic curve was 0.849 for letter naming, 0.892 for color naming, 0.971 for number naming, 0.887 for picture naming, and 0.965 totally. The overall sensitivity and specificity was 1 and was 0.79, respectively. The highest sensitivity and specificity were related to number naming (1 and 0.90, respectively.Conclusion: Findings showed that the rapid automized naming test could diagnose good readers from dyslexics appropriately.
Ageing study of protection automation components of Olkiluoto nuclear power plant

International Nuclear Information System (INIS)

Simola, K.; Haenninen, S.

1993-07-01

A study on ageing of reactor protection system of the Olkiluoto nuclear power plant is described. The objective of the study was to present an ageing analysis approach and apply in to the automation chains of reactor protection system of the Olkiluoto nuclear power plant. The study includes the measuring instrumentation, the protection logics, and the control electronics of some pumps and valves. The analysis is based on the information collected on the structure of the system, environmental conditions and maintenance practices of components, and operating experience. Based on this information, the possible ageing effects of equipment and their safety significance are evaluated. (orig.). (15 refs., 16 figs., 12 tabs.)
Automation drying unit molybdenum-zirconium gel radioisotope production technetium-99M for nuclear medicine

International Nuclear Information System (INIS)

Chakrova, Y.; Khromushin, I.; Medvedeva, Z.; Fettsov, I.

2014-01-01

Full text : Since 2001 the Institute of Nuclear Physics of the Republic of Kazakhstan has began production of radiopharmaceutical based on technetium-99m from irradiated reactor WWR-K of natural molybdenum, which allows to obtain a solution of technetium-99m of the required quality and high volume activity. In 2013 an automated system is started, which is unique and urgent task is to develop algorithms and software in Python, as well as the manufacture of certain elements of technological systems for automated production
Automated approach to nuclear facility safeguards effectiveness evaluation

International Nuclear Information System (INIS)

1977-01-01

Concern over the security of nuclear facilities has generated a need for a reliable, time efficient, and easily applied method of evaluating the effectiveness of safeguards systems. Such an evaluation technique could be used (1) by the Nuclear Regulatory Commission to evaluate a licensee's proposal, (2) to assess the security status of a system, or (3) to design and/or upgrade nuclear facilities. The technique should be capable of starting with basic information, such as the facility layout and performance parameters for physical protection components, and analyzing that information so that a reliable overall facility evaluation is obtained. Responding to this expressed need, an automated approach to facility safeguards effectiveness evaluation has been developed. This procedure consists of a collection of functional modules for facility characterization, critical path generation, and path evaluation combined into a continuous stream of operations. The technique has been implemented on an interactive computer-timesharing system and makes use of computer graphics for the handling and presentation of information. Using this technique a thorough facility evaluation can be made by systematically varying parameters that characterize the physical protection components of a facility according to changes in perceived adversary attributes and strategy, environmental conditions, and site status
The role of automation and humans in nuclear power plants

International Nuclear Information System (INIS)

1992-10-01

The document is the result of a series of advisory and consultants meetings held within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation in 1989-1990. It provides a basis for assigning functions to men and machines and for achieving a desirable balance. It should be particularly useful to designers of of new systems, where a large number of assignment decisions will have to be identified, taken and documented. In addition, the methodology can be used by utilities for plant modifications and upgrades. The document may also be employed for examining existing assignments in a system since the principles on which the document is based are generally applicable. The document may be useful to those who develop requirement specifications for automation, to technology designers who design automated machines, and to researchers who intend to further refine the function assignment methodology. Refs, figs and tabs
A project in support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho [and others

2005-12-15

Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate.
A project in support of Nuclear Technology Cooperation

International Nuclear Information System (INIS)

Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho

2005-12-01

Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate
Development of an automated testing system for verification and validation of nuclear data

International Nuclear Information System (INIS)

Triplett, B. S.; Anghaie, S.; White, M. C.

2008-01-01

Verification and validation of nuclear data is critical to the accuracy of both stochastic and deterministic particle transport codes. In order to effectively test a set of nuclear data, the data must be applied to a wide variety of transport problems. Performing this task in a timely, efficient manner is tedious. The nuclear data team at Los Alamos National Laboratory (LANL) in collaboration with the University of Florida is developing a methodology to automate the process of nuclear data verification and validation. The International Criticality Safety Benchmark Experiment Project (ICSBEP) provides a set of criticality problems that may be used to evaluate nuclear data. This process tests a number of data libraries using cases from the ICSBEP benchmark set to demonstrate how automation of these tasks may reduce errors and increase efficiency. The process is driven by an integrated set of Python scripts. Material and geometry data may be read from an existing code input file to generate a standardized template or the template may be generated directly by the user The user specifies the desired precision and other vital problem parameters. The Python scripts generate input decks for multiple transport codes from these templates, run and monitor individual jobs, and parse the relevant output. This output can then be used to generate reports directly or can be stored into a database for later analysis. This methodology eases the burden on the user by reducing the amount of time and effort required for obtaining and compiling calculation results. (authors)
Automated nuclear material recovery and decontamination of large steel dynamic experiment containers

International Nuclear Information System (INIS)

Dennison, D.K.; Gallant, D.A.; Nelson, D.C.; Stovall, L.A.; Wedman, D.E.

1999-01-01

A key mission of the Los Alamos National Laboratory (LANL) is to reduce the global nuclear danger through stockpile stewardship efforts that ensure the safety and reliability of nuclear weapons. In support of this mission LANL performs dynamic experiments on special nuclear materials (SNM) within large steel containers. Once these experiments are complete, these containers must be processed to recover residual SNM and to decontaminate the containers to below low level waste (LLW) disposal limits which are much less restrictive for disposal purposes than transuranic (TRU) waste limits. The purpose of this paper is to describe automation efforts being developed by LANL for improving the efficiency, increasing worker safety, and reducing worker exposure during the material cleanout and recovery activities performed on these containers
Development of an automated core model for nuclear reactors

International Nuclear Information System (INIS)

Mosteller, R.D.

1998-01-01

This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The objective of this project was to develop an automated package of computer codes that can model the steady-state behavior of nuclear-reactor cores of various designs. As an added benefit, data produced for steady-state analysis also can be used as input to the TRAC transient-analysis code for subsequent safety analysis of the reactor at any point in its operating lifetime. The basic capability to perform steady-state reactor-core analysis already existed in the combination of the HELIOS lattice-physics code and the NESTLE advanced nodal code. In this project, the automated package was completed by (1) obtaining cross-section libraries for HELIOS, (2) validating HELIOS by comparing its predictions to results from critical experiments and from the MCNP Monte Carlo code, (3) validating NESTLE by comparing its predictions to results from numerical benchmarks and to measured data from operating reactors, and (4) developing a linkage code to transform HELIOS output into NESTLE input
Specific Methods of Information Security for Nuclear Materials Control and Accounting Automate Systems

Directory of Open Access Journals (Sweden)

Konstantin Vyacheslavovich Ivanov

2013-02-01

Full Text Available The paper is devoted to specific methods of information security for nuclear materials control and accounting automate systems which is not required of OS and DBMS certifications and allowed to programs modification for clients specific without defenses modification. System ACCORD-2005 demonstrates the realization of this method.
Rapid enumeration of low numbers of moulds in tea based drinks using an automated system.

Science.gov (United States)

Tanaka, Kouichi; Yamaguchi, Nobuyasu; Baba, Takashi; Amano, Norihide; Nasu, Masao

2011-01-31

Aseptically prepared cold drinks based on tea have become popular worldwide. Contamination of these drinks with harmful microbes is a potential health problem because such drinks are kept free from preservatives to maximize aroma and flavour. Heat-tolerant conidia and ascospores of fungi can survive pasteurization, and need to be detected as quickly as possible. We were able to rapidly and accurately detect low numbers of conidia and ascospores in tea-based drinks using fluorescent staining followed by an automated counting system. Conidia or ascospores were inoculated into green tea and oolong tea, and samples were immediately filtered through nitrocellulose membranes (pore size: 0.8 μm) to concentrate fungal propagules. These were transferred onto potato dextrose agar and incubated for 23 h at 28 °C. Fungi germinating on the membranes were fluorescently stained for 30 min. The stained mycelia were counted selectively within 90s using an automated counting system (MGS-10LD; Chuo Electric Works, Osaka, Japan). Very low numbers (1 CFU/100ml) of conidia or ascospores could be rapidly counted, in contrast to traditional labour intensive techniques. All tested mould strains were detected within 24h while conventional plate counting required 72 h for colony enumeration. Counts of slow-growing fungi (Cladosporium cladosporioides) obtained by automated counting and by conventional plate counting were close (r(2) = 0.986). Our combination of methods enables counting of both fast- and slow-growing fungi, and should be useful for microbiological quality control of tea-based and also other drinks. Copyright © 2011 Elsevier B.V. All rights reserved.
AUTOMATED PROCESS MONITORING: APPLYING PROVEN AUTOMATION TECHNIQUES TO INTERNATIONAL SAFEGUARDS NEEDS

International Nuclear Information System (INIS)

O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Devol, Timothy A.; Egorov, Oleg; Clements, John P.

2008-01-01

Identification and quantification of specific alpha- and beta-emitting radionuclides in complex liquid matrices is highly challenging, and is typically accomplished through laborious wet chemical sample preparation and separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, gas proportional counting, alpha energy analysis, mass spectrometry). Analytical results may take days or weeks to report. Chains of custody and sample security measures may also complicate or slow the analytical process. When an industrial process-scale plant requires the monitoring of specific radionuclides as an indication of the composition of its feed stream or of plant performance, radiochemical measurements must be fast, accurate, and reliable. Scientists at Pacific Northwest National Laboratory have assembled a fully automated prototype Process Monitor instrument capable of a variety of tasks: automated sampling directly from a feed stream, sample digestion/analyte redox adjustment, chemical separations, radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results could be immediately transmitted to on- or off-site locations. The development of a rapid radiochemical Process Monitor for 99Tc in Hanford tank waste processing streams, capable of performing several measurements per hour, will be discussed in detail. More recently, the automated platform was modified to perform measurements of 90Sr in Hanford tank waste stimulant. The system exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs
A nationwide web-based automated system for early outbreak detection and rapid response in China

Directory of Open Access Journals (Sweden)

Yilan Liao

2011-03-01

Full Text Available Timely reporting, effective analyses and rapid distribution of surveillance data can assist in detecting the aberration of disease occurrence and further facilitate a timely response. In China, a new nationwide web-based automated system for outbreak detection and rapid response was developed in 2008. The China Infectious Disease Automated-alert and Response System (CIDARS was developed by the Chinese Center for Disease Control and Prevention based on the surveillance data from the existing electronic National Notifiable Infectious Diseases Reporting Information System (NIDRIS started in 2004. NIDRIS greatly improved the timeliness and completeness of data reporting with real time reporting information via the Internet. CIDARS further facilitates the data analysis, aberration detection, signal dissemination, signal response and information communication needed by public health departments across the country. In CIDARS, three aberration detection methods are used to detect the unusual occurrence of 28 notifiable infectious diseases at the county level and to transmit that information either in real-time or on a daily basis. The Internet, computers and mobile phones are used to accomplish rapid signal generation and dissemination, timely reporting and reviewing of the signal response results. CIDARS has been used nationwide since 2008; all Centers for Disease Control and Prevention (CDC in China at the county, prefecture, provincial and national levels are involved in the system. It assists with early outbreak detection at the local level and prompts reporting of unusual disease occurrences or potential outbreaks to CDCs throughout the country.
A project in support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho (and others)

2005-12-15

Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate.
The use of an automated flight test management system in the development of a rapid-prototyping flight research facility

Science.gov (United States)

Duke, Eugene L.; Hewett, Marle D.; Brumbaugh, Randal W.; Tartt, David M.; Antoniewicz, Robert F.; Agarwal, Arvind K.

1988-01-01

An automated flight test management system (ATMS) and its use to develop a rapid-prototyping flight research facility for artificial intelligence (AI) based flight systems concepts are described. The ATMS provides a flight test engineer with a set of tools that assist in flight planning and simulation. This system will be capable of controlling an aircraft during the flight test by performing closed-loop guidance functions, range management, and maneuver-quality monitoring. The rapid-prototyping flight research facility is being developed at the Dryden Flight Research Facility of the NASA Ames Research Center (Ames-Dryden) to provide early flight assessment of emerging AI technology. The facility is being developed as one element of the aircraft automation program which focuses on the qualification and validation of embedded real-time AI-based systems.
An automated solution enrichment system for uranium analysis

International Nuclear Information System (INIS)

Jones, S.A.; Sparks, R.; Sampson, T.; Parker, J.; Horley, E.; Kelly, T.

1993-01-01

An automated Solution Enrichment system (SES) for analysis of Uranium and U-235 isotopes in process samples has been developed through a joint effort between Los Alamos National Laboratory and Martin Marietta Energy systems, Portsmouth Gaseous Diffusion Plant. This device features an advanced robotics system which in conjuction with stabilized passive gamma-ray and X-ray fluorescence detectors provides for rapid, non-destructive analyses of process samples for improved special nuclear material accountability and process control
Process automation

International Nuclear Information System (INIS)

Moser, D.R.

1986-01-01

Process automation technology has been pursued in the chemical processing industries and to a very limited extent in nuclear fuel reprocessing. Its effective use has been restricted in the past by the lack of diverse and reliable process instrumentation and the unavailability of sophisticated software designed for process control. The Integrated Equipment Test (IET) facility was developed by the Consolidated Fuel Reprocessing Program (CFRP) in part to demonstrate new concepts for control of advanced nuclear fuel reprocessing plants. A demonstration of fuel reprocessing equipment automation using advanced instrumentation and a modern, microprocessor-based control system is nearing completion in the facility. This facility provides for the synergistic testing of all chemical process features of a prototypical fuel reprocessing plant that can be attained with unirradiated uranium-bearing feed materials. The unique equipment and mission of the IET facility make it an ideal test bed for automation studies. This effort will provide for the demonstration of the plant automation concept and for the development of techniques for similar applications in a full-scale plant. A set of preliminary recommendations for implementing process automation has been compiled. Some of these concepts are not generally recognized or accepted. The automation work now under way in the IET facility should be useful to others in helping avoid costly mistakes because of the underutilization or misapplication of process automation. 6 figs
The Rotary Zone Thermal Cycler: A Low-Power System Enabling Automated Rapid PCR

Science.gov (United States)

Bartsch, Michael S.; Renzi, Ronald F.; Van de Vreugde, James L.; Kim, Hanyoup; Knight, Daniel L.; Sinha, Anupama; Branda, Steven S.; Patel, Kamlesh D.

2015-01-01

Advances in molecular biology, microfluidics, and laboratory automation continue to expand the accessibility and applicability of these methods beyond the confines of conventional, centralized laboratory facilities and into point of use roles in clinical, military, forensic, and field-deployed applications. As a result, there is a growing need to adapt the unit operations of molecular biology (e.g., aliquoting, centrifuging, mixing, and thermal cycling) to compact, portable, low-power, and automation-ready formats. Here we present one such adaptation, the rotary zone thermal cycler (RZTC), a novel wheel-based device capable of cycling up to four different fixed-temperature blocks into contact with a stationary 4-microliter capillary-bound sample to realize 1-3 second transitions with steady state heater power of less than 10 W. We demonstrate the utility of the RZTC for DNA amplification as part of a highly integrated rotary zone PCR (rzPCR) system that uses low-volume valves and syringe-based fluid handling to automate sample loading and unloading, thermal cycling, and between-run cleaning functionalities in a compact, modular form factor. In addition to characterizing the performance of the RZTC and the efficacy of different online cleaning protocols, we present preliminary results for rapid single-plex PCR, multiplex short tandem repeat (STR) amplification, and second strand cDNA synthesis. PMID:25826708
The rotary zone thermal cycler: a low-power system enabling automated rapid PCR.

Directory of Open Access Journals (Sweden)

Michael S Bartsch

Full Text Available Advances in molecular biology, microfluidics, and laboratory automation continue to expand the accessibility and applicability of these methods beyond the confines of conventional, centralized laboratory facilities and into point of use roles in clinical, military, forensic, and field-deployed applications. As a result, there is a growing need to adapt the unit operations of molecular biology (e.g., aliquoting, centrifuging, mixing, and thermal cycling to compact, portable, low-power, and automation-ready formats. Here we present one such adaptation, the rotary zone thermal cycler (RZTC, a novel wheel-based device capable of cycling up to four different fixed-temperature blocks into contact with a stationary 4-microliter capillary-bound sample to realize 1-3 second transitions with steady state heater power of less than 10 W. We demonstrate the utility of the RZTC for DNA amplification as part of a highly integrated rotary zone PCR (rzPCR system that uses low-volume valves and syringe-based fluid handling to automate sample loading and unloading, thermal cycling, and between-run cleaning functionalities in a compact, modular form factor. In addition to characterizing the performance of the RZTC and the efficacy of different online cleaning protocols, we present preliminary results for rapid single-plex PCR, multiplex short tandem repeat (STR amplification, and second strand cDNA synthesis.

Evaluation of operators' mental workload of human-system interface automation in the advanced nuclear power plants

International Nuclear Information System (INIS)

Jou, Y.-T.; Yenn, T.-C.; Lin, Chiuhsiang Joe; Yang, C.-W.; Chiang, C.-C.

2009-01-01

It has been expected that the automation of certain tasks in a control room would help decrease operators' mental workload, enhance situation awareness, and improve the whole system performance. However, there have been too many automation-induced system failures that would warrant a fresh look on the influences of automation. Automation problems include the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills. This study evaluates operators' mental workload and system performance during a human-system interface (HSI) automation in an advanced nuclear power plant (NPP). The reactor shutdown task and alarm reset task simulations were conducted in this study to evaluate operators' mental workload and performance. The results of this study indicated that for ensuring safe operating in NPPs, the design of automation needs to be carefully implemented. Task characteristics and degrees of automation should be carefully evaluated while designing HSIs. The reactor shutdown tasks studied in this paper suggest that a high level of automation design for the long period and low workload would be sufficient. On the other hand, the degree of automation of alarm reset task does not show a significant difference to the operator's mental workload. In conclusion, the human-system interface automation in advanced NPPs is suggested to be more flexible and needs to be continually improved.
A Comparison of Anti-Nuclear Antibody Quantification Using Automated Enzyme Immunoassays and Immunofluorescence Assays

DEFF Research Database (Denmark)

Baronaite, Renata; Engelhart, Merete; Mørk Hansen, Troels

2014-01-01

using IFA and automated EIA techniques. The IFA results generated by two independent laboratories were compared with the EIA results from antibodies against double-stranded DNA (dsDNA), from ANA screening, and from tests of the seven included subantigens. The final IFA and EIA results for 386 unique......, with Cohen's kappa value of 0.30 (95% confidence interval (CI) = 0.14-0.46), which decreased to 0.23 (95% CI = 0.06-0.40) when the results for dsDNA were omitted. The EIA method was less reliable for assessing nuclear and speckled reactivity patterns, whereas the IFA method presented difficulties detecting...... dsDNA and Ro activity. The automated EIA method was performed in a similar way to the conventional IFA method using HEp-2 cells; thus, automated EIA may be used as a screening test....
Automation of the helium jet transport system for nuclear recoil products

International Nuclear Information System (INIS)

Bellido, Luis F.; Pedrosa, Paulo S.

1996-09-01

A computer code and an interface hardware to automate the acquisition data and the sample changer in a helium jet transport system of recoil nucleus was developed for an IBM or compatible personal microcomputer. The software works with a Spectrum-ACE/ADCAM ORTEC's multichannel analysers and the interface card uses the 03EFh port to command the sample changer. This system allows to measure, by gamma spectrometry, radionuclides with half-lives of order of seconds produced from nuclear reactions. (author)
A Project in Support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Hwang, Deok Ku; Kim, Kyoung Pyo; Ko, Young Chel [and others

2006-12-15

Establish strategies of international cooperation in an effect to promote our nation's leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. Using the INIS output data, it has provided domestic users with searching. Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing.
Automated system for recording reports in nuclear medicine

International Nuclear Information System (INIS)

Machida, Kikuo; Hayashi, Sanshin; Watari, Tsutomu; Akaike, Akira; Oyama, Kazuyuki

1976-01-01

In order to overcome the rapid expansion of nuclear medicine as a diagnostic tool, we developed the system called ''Radiological Bunin Report System'' to record the clinical report in nuclear medicine automatically using the Tosbac 40 time sharing system electronic computer and the keymat-editor (DTZ 0008A). The system is composed of three modules, that is, reader, editor and writer. The module of the reader is used to register sentences and terms by which one can easily add to or change the registered dictionary. The module of the editor is used to make an intermediate file of radiological reports. With the aid of a keymateditor a radiologist puts in the necessary sentences and terms usually in the following order: procedure, interpretation, diagnosis, recommendation and doctor's code, thus making the intermediate file. In this procedure error message, if any, may be printed out on terminal typewriter. Finally the module of the writer is used to edit the intermediate file and to make sentences. Having stored several clinical reports, the computer automatically produces as many of the English written reports as one wants by printing order. By this system we are able to save man power in the hospital, and the radiological report is standardized. Furthermore, in view of the rapid progress and change of nuclear medicine, it is very important that a radiologist is able to change and add sentences and terms on a keymat very easily so that the system may be kept up-to-date and valuable. We believe this is one of the most characteristic advantages of the system. (auth.)
Automated system for recording reports in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Machida, K; Hayashi, S; Watari, T; Akaike, A; Oyama, K [Tokyo Univ. (Japan). Faculty of Medicine

1976-07-01

In order to overcome the rapid expansion of nuclear medicine as a diagnostic tool, we developed the system called ''Radiological Bunin Report System'' to record the clinical report in nuclear medicine automatically using the Tosbac 40 time sharing system electronic computer and the keymat-editor (DTZ 0008A). The system is composed of three modules, that is, reader, editor and writer. The module of the reader is used to register sentences and terms by which one can easily add to or change the registered dictionary. The module of the editor is used to make an intermediate file of radiological reports. With the aid of a keymateditor a radiologist puts in the necessary sentences and terms usually in the following order: procedure, interpretation, diagnosis, recommendation and doctor's code, thus making the intermediate file. In this procedure error message, if any, may be printed out on terminal typewriter. Finally the module of the writer is used to edit the intermediate file and to make sentences. Having stored several clinical reports, the computer automatically produces as many of the English written reports as one wants by printing order. By this system we are able to save man power in the hospital, and the radiological report is standardized. Furthermore, in view of the rapid progress and change of nuclear medicine, it is very important that a radiologist is able to change and add sentences and terms on a keymat very easily so that the system may be kept up-to-date and valuable. We believe this is one of the most characteristic advantages of the system.
Remote-automation of nuclear power plant equipment inspection and maintenance

International Nuclear Information System (INIS)

Sasaki, Masayoshi; Kawamura, Hironobu; Nakano, Yoshiyuki; Izumi, Shigeru.

1984-01-01

The remotely operated automation of the checkup and maintenance of nuclear power generation facilities has largely contributed to the rise of capacity ratio of plants due to the shortening of regular inspection period and to the reduction of radiation exposure dose during working, the labor saving in working and so on. In this paper, the new technologies adopted in an automatic fuel exchanger, a remotely operated automatic CRD exchanger, a new type channel handling machine, pressure-withstanding main steam line plugs and so on for No.2 plant in the Fukushima No.2 Nuclear Power Station, Tokyo Electric Power Co., Inc., are reported. Besides, the state of development of new remotely operated automatic machines for nuclear power use, such as CRD disassembling and cleaning device, volume reduction equipment for spent fuel channel boxes and control rods, multi-functional robots for use under high radiation and so on is described. Also the trend of development of latest robot technology which will be put in practical use in near future is outlined, such as a running manipulator for checkup and inspection, a variable form crawler vehicle and a five-leg movable manipulator. (Kako, I.)
Simulation and Automation of Microwave Frequency Control in Dynamic Nuclear Polarization for Solid Polarized Targets

Science.gov (United States)

Perera, Gonaduwage; Johnson, Ian; Keller, Dustin

2017-09-01

Dynamic Nuclear Polarization (DNP) is used in most of the solid polarized target scattering experiments. Those target materials must be irradiated using microwaves at a frequency determined by the difference in the nuclear Larmor and electron paramagnetic resonance (EPR) frequencies. But the resonance frequency changes with time as a result of radiation damage. Hence the microwave frequency should be adjusted accordingly. Manually adjusting the frequency can be difficult, and improper adjustments negatively impact the polarization. In order to overcome these difficulties, two controllers were developed which automate the process of seeking and maintaining the optimal frequency: one being a standalone controller for a traditional DC motor and the other a LabVIEW VI for a stepper motor configuration. Further a Monte-Carlo simulation was developed which can accurately model the polarization over time as a function of microwave frequency. In this talk, analysis of the simulated data and recent improvements to the automated system will be presented. DOE.
Automation of technical specification monitoring for nuclear power plants

International Nuclear Information System (INIS)

Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

1986-01-01

The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)
A Project in Support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Hwang, Deok Ku; Kim, Kyoung Pyo; Ko, Young Chel (and others)

2006-12-15

Establish strategies of international cooperation in an effect to promote our nation's leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. Using the INIS output data, it has provided domestic users with searching. Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing.
Rapid Prototyping of a Cyclic Olefin Copolymer Microfluidic Device for Automated Oocyte Culturing.

Science.gov (United States)

Berenguel-Alonso, Miguel; Sabés-Alsina, Maria; Morató, Roser; Ymbern, Oriol; Rodríguez-Vázquez, Laura; Talló-Parra, Oriol; Alonso-Chamarro, Julián; Puyol, Mar; López-Béjar, Manel

2017-10-01

Assisted reproductive technology (ART) can benefit from the features of microfluidic technologies, such as the automation of time-consuming labor-intensive procedures, the possibility to mimic in vivo environments, and the miniaturization of the required equipment. To date, most of the proposed approaches are based on polydimethylsiloxane (PDMS) as platform substrate material due to its widespread use in academia, despite certain disadvantages, such as the elevated cost of mass production. Herein, we present a rapid fabrication process for a cyclic olefin copolymer (COC) monolithic microfluidic device combining hot embossing-using a low-temperature cofired ceramic (LTCC) master-and micromilling. The microfluidic device was suitable for trapping and maturation of bovine oocytes, which were further studied to determine their ability to be fertilized. Furthermore, another COC microfluidic device was fabricated to store sperm and assess its quality parameters over time. The study herein presented demonstrates a good biocompatibility of the COC when working with gametes, and it exhibits certain advantages, such as the nonabsorption of small molecules, gas impermeability, and low fabrication costs, all at the prototyping and mass production scale, thus taking a step further toward fully automated microfluidic devices in ART.
Automated rapid analysis for dioxins and PCBs in food, feedingstuff and environmental matrices

Energy Technology Data Exchange (ETDEWEB)

Hoelscher, K.; Maulshagen, A.; Behnisch, P.A. [eurofins-GfA, Muenster (Germany); Shirkhan, H. [Fluid Management Systems Inc., Waltham, MA (United States); Lieck, G. [University of Applied Science, Steinfurt (Germany)

2004-09-15

Today there is a need to develop high throughput specific and sensitive methods for the determination of dioxins, dioxin-like PCBs and indicator-PCBs to ensure their rapid and reliable quantification in several kinds of food and feedingstuffs. Ideally one method would fit for several matrices with highest quality standards and with the possibility of a cost/time-effective samplehandling. However, generally in case of the numerous different PCDD/Fs, dioxin-like PCBs and indicator-PCBs as well as the large concentration range to cover this is quite difficult to fulfill. The implementation of an automated sample-treatment flow process (''dioxin street''), which contains an accelerated solvent extraction (ASE), a Power-Prep workstation (Fluid Management Systems, FMS) for automated clean-up, a Syncore Polyvap (Buechi, Switzerland) for solvent evaporation and a HRGC/HRMS (VG AutoSpec) analysis as detection method for several kinds of different matrices is described here. The aim of the present study is to confirm the high quality, low limits of quantification (LOQ), low PCB background levels and reliability of the Power-Prep system in combination with ASE extraction for dioxins, dioxin-like PCBs and indicator-PCBs.
Intelligent control and automation technology for nuclear applications

International Nuclear Information System (INIS)

Kim, Jae Hui; Huh, Young Hwan; Lee, Jang Soo; Kim, Ko Ryeo; Cha, Kyoung Ho; Lee, Jae Cheol; Dong, In Sook

1993-01-01

This project intends to establish the basic technology of intelligent control and automation to be applied to the next generation nuclear plant. For that, the research status of those technologies is surveyed for various application areas at first. The characteristics and availability of those techniques such as neural network, fuzzy rule based control and reasoning, multimedia, real-time software and qualitative modelling are studied through a series of simulations and experiments. By integrating each technologies studied above, we developed a hierarchical, intelligent control system for an autonomous mobile robot as a test bed. The system is composed of several modules of software and hardware subsystems, which are implemented by use of the intelligent techniques. Through the analysis of the results and experiences, we investigated the feasibility of application of the basic technology to the next generation plant. (Author)
A cellular automation model for the change of public attitude regarding nuclear energy

International Nuclear Information System (INIS)

Ohnishi, Teruaki

1991-01-01

A cellular automation model was constructed to investigate how public opinion on nuclear energy in Japan depends upon the information environment and personal communication between people. From simulation with this model, the following become clear; (i) society is a highly non-linear system with a self-organizing potential: (ii) in a society composed of one type of constituent member with homogeneous characteristics, the trend of public opinion is substantially changed only when the effort to ameliorate public acceptance over a long period of time, by means such as education, persuasion and advertisement, exceeds a certain threshold, and (iii) in the case when the amount of information on nuclear risk released from the newsmedia is reduced continuously from now on, the acceptability of nuclear energy is significantly improved so far as the extent of the reduction exceeds a certain threshold. (author)
A cellular automation model for the change of public attitude regarding nuclear energy

Energy Technology Data Exchange (ETDEWEB)

Ohnishi, Teruaki (CRC Research Inst., Chiba (Japan))

1991-01-01

A cellular automation model was constructed to investigate how public opinion on nuclear energy in Japan depends upon the information environment and personal communication between people. From simulation with this model, the following become clear; (i) society is a highly non-linear system with a self-organizing potential: (ii) in a society composed of one type of constituent member with homogeneous characteristics, the trend of public opinion is substantially changed only when the effort to ameliorate public acceptance over a long period of time, by means such as education, persuasion and advertisement, exceeds a certain threshold, and (iii) in the case when the amount of information on nuclear risk released from the newsmedia is reduced continuously from now on, the acceptability of nuclear energy is significantly improved so far as the extent of the reduction exceeds a certain threshold. (author).
Driver Psychology during Automated Platooning

NARCIS (Netherlands)

Heikoop, D.D.

2017-01-01

With the rapid increase in vehicle automation technology, the call for understanding how humans behave while driving in an automated vehicle becomes more urgent. Vehicles that have automated systems such as Lane Keeping Assist (LKA) or Adaptive Cruise Control (ACC) not only support drivers in their
Automated derivation of failure symptoms for diagnosis of nuclear plant

International Nuclear Information System (INIS)

Washio, T.; Kitamura, M.; Kotajima, K.; Sugiyama, K.

1986-01-01

A method of automated derivation of failure symptoms was developed as an approach to computer-aided failure diagnosis in a nuclear power plant. The automated derivation is realized using a knowledge representation called the semantic network (S-net). The purpose of this paper is to demonstrate the applicability of the S-net representation as a basic tool for deriving failure symptoms. If one can generate symptoms automatically, the computer-aided plant safety analysis and diagnosis can be performed easily by evaluating the influence of the failures on the whole plant. A specific description format called a 'network list' was introduced to implement the knowledge of the structure of the plant. The failure symptoms are derived automatically, based on the knowledge of the structure of the plant, using a PROLOG-based database handling system. This approach allows us to derive the failure symptoms of the plant without using conventional event-chain models (e.g. a cause-consequence tree) which are subject to human errors in their design and implementation. Applicability of this method was evaluated with a simulation model of the dynamics of the secondary system of a PWR. (author)
Shielded cells transfer automation

International Nuclear Information System (INIS)

Fisher, J.J.

1984-01-01

Nuclear waste from shielded cells is removed, packaged, and transferred manually in many nuclear facilities. Radiation exposure is absorbed by operators during these operations and limited only through procedural controls. Technological advances in automation using robotics have allowed a production waste removal operation to be automated to reduce radiation exposure. The robotic system bags waste containers out of glove box and transfers them to a shielded container. Operators control the system outside the system work area via television cameras. 9 figures
A portable, automated, inexpensive mass and balance calibration system

International Nuclear Information System (INIS)

Maxwell, S.L. III; Clark, J.P.

1987-01-01

Reliable mass measurements are essential for a nuclear production facility or process control laboratory. DOE Order 5630.2 requires that traceable standards be used to calibrate and monitor equipment used for nuclear material measurements. To ensure the reliability of mass measurements and to comply with DOE traceability requirements, a portable, automated mass and balance calibration system is used at the Savannah River Plant. Automation is achieved using an EPSON HX-20 notebook computer, which can be operated via RS232C interfacing to electronic balances or function with manual data entry if computer interfacing is not feasible. This economical, comprehensive, user-friendly system has three main functions in a mass measurement control program (MMCP): balance certification, calibration of mass standards, and daily measurement of traceable standards. The balance certification program tests for accuracy, precision, sensitivity, linearity, and cornerloading versus specific requirements. The mass calibration program allows rapid calibration of inexpensive mass standards traceable to certified Class S standards. This MMCP permits daily measurement of traceable standards to monitor the reliability of balances during routine use. The automated system verifies balance calibration, stores results for future use, and provides a printed control chart of the stored data. Another feature of the system permits three different weighing routines that accommodate their need for varying degrees of reliability in routine weighing operations
A portable, automated, inexpensive mass and balance calibration system

International Nuclear Information System (INIS)

Maxwell, S.L. III; Clark, J.P.

1987-01-01

Reliable mass measurements are essential for a nuclear production facility or process control laboratory. DOE Order 5630.2 requires that traceable standards be used to calibrate and monitor equipment used for nuclear material measurements. To ensure the reliability of mass measurements and to comply with DOE traceable requirements, a portable, automated mass and balance calibration system is used at the Savannah River Plant. Automation is achieved using an EPSON HX-20 notebook computer, which can be operated via RS232C interfacing to electronic balances or function with manual data entry if computer interfacing is not feasible. This economical, comprehensive, user-friendly system has three main functions in a mass measurement control program (MMCP): balance certification, calibration of mass standards, and daily measurement of traceable standards. The balance certification program tests for accuracy, precision, sensitivity, linearity, and cornerloading versus specific requirements. The mass calibration program allows rapid calibration of inexpensive mass standards traceable to certified Class S standards. This MMCP permits daily measurement of traceable standards to monitor the reliability of balances during routine use. The automated system verifies balance calibration, stores results for future use, and provides a printed control chart of the stored data. Another feature of the system permits three different weighing routines that accommodate our need for varying degrees of reliability in routine weighing operations. 1 ref

A microfluidics-based technique for automated and rapid labeling of cells for flow cytometry

International Nuclear Information System (INIS)

Patibandla, Phani K; Estrada, Rosendo; Kannan, Manasaa; Sethu, Palaniappan

2014-01-01

Flow cytometry is a powerful technique capable of simultaneous multi-parametric analysis of heterogeneous cell populations for research and clinical applications. In recent years, the flow cytometer has been miniaturized and made portable for application in clinical- and resource-limited settings. The sample preparation procedure, i.e. labeling of cells with antibodies conjugated to fluorescent labels, is a time consuming (∼45 min) and labor-intensive procedure. Microfluidics provides enabling technologies to accomplish rapid and automated sample preparation. Using an integrated microfluidic device consisting of a labeling and washing module, we demonstrate a new protocol that can eliminate sample handling and accomplish sample and reagent metering, high-efficiency mixing, labeling and washing in rapid automated fashion. The labeling module consists of a long microfluidic channel with an integrated chaotic mixer. Samples and reagents are precisely metered into this device to accomplish rapid and high-efficiency mixing. The mixed sample and reagents are collected in a holding syringe and held for up to 8 min following which the mixture is introduced into an inertial washing module to obtain ‘analysis-ready’ samples. The washing module consists of a high aspect ratio channel capable of focusing cells to equilibrium positions close to the channel walls. By introducing the cells and labeling reagents in a narrow stream at the center of the channel flanked on both sides by a wash buffer, the elution of cells into the wash buffer away from the free unbound antibodies is accomplished. After initial calibration experiments to determine appropriate ‘holding time’ to allow antibody binding, both modules were used in conjunction to label MOLT-3 cells (T lymphoblast cell line) with three different antibodies simultaneously. Results confirm no significant difference in mean fluorescence intensity values for all three antibodies labels (p < 0.01) between the
Automated ultrasonic inspection using PULSDAT

International Nuclear Information System (INIS)

Naybour, P.J.

1992-01-01

PULSDAT (Portable Ultrasonic Data Acquisition Tool) is a system for recording the data from single probe automated ultrasonic inspections. It is one of a range of instruments and software developed by Nuclear Electric to carry out a wide variety of high quality ultrasonic inspections. These vary from simple semi-automated inspections through to multi-probe, highly automated ones. PULSDAT runs under the control of MIPS software, and collects data which is compatible with the GUIDE data display system. PULSDAT is therefore fully compatible with Nuclear Electric's multi-probe inspection systems and utilises all the reliability and quality assurance of the software. It is a rugged, portable system that can be used in areas of difficult access. The paper discusses the benefits of automated inspection and gives an outline of the main features of PULSDAT. Since April 1990 PULSDAT has been used in several applications within Nuclear Electric and this paper presents two examples: the first is a ferritic set-through nozzle and the second is an austenitic fillet weld. (Author)
HedgeHOGS: A Rapid Nuclear Hedge Sizing and Analysis Tool

Energy Technology Data Exchange (ETDEWEB)

Reynolds, Adam F. [United States Military Academy, West Point, NY (United States); Steinfeldt, Bradley Alexander [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Lafleur, Jarret Marshall [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Hawley, Marilyn F. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Shannon, Lisa M. [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

2017-07-01

The U.S. nuclear stockpile hedge is an inventory of non-deployed nuclear warheads and a force structure capable of deploying those warheads. Current guidance is to retain this hedge to mitigate the risk associated with the technical failure of any single warhead type or adverse geopolitical developments that could require augmentation of the force. The necessary size of the hedge depends on the composition of the nuclear stockpile and assumed constraints. Knowing the theoretical minimum hedge given certain constraints is useful when considering future weapons policy. HedgeHOGS, an Excel-based tool, was developed to enable rapid calculation of the minimum hedge size associated with varying active stockpile composition and hedging strategies.
Some aspects of automation in nuclear industry

International Nuclear Information System (INIS)

Padegaonkar, Varsha; Modi, R.K.; Venkatesh, D.; Ramkumar, M.S.; Ramanujam, A.; Dhumwad, R.K.

1990-01-01

Operations with radioactive materials (radioactive solutions, irradiated nuclear fuels, waste, etc.) need very specialised remote handling equipment. There is an increasing tendency to automate jobs that can clearly be planned. These include a surprisingly large number of tasks - especially if one considers using flexible robotic systems that can be performed automatically, remotely safely. One such system, namely, a computer controlled robotic radioactive sample solution handling system is described. It basically consists of a cylindrical co-ordinate type robot (LABOT), a computer controlled storage vault of chemical samples, decapping-capping device for bottles and software. An attempt is being made to give the technician a menu of possible operations and help him for coherent chain of operations. The computer, in addition to operating the robot, the storage vault and other accessories, will also log the operations performed and maintain records. The operations carried out by the robot are that of a chemical laboratory technician like sampling, aliquoting, weighing, storage and recovery of samples, maintenance of records, etc.. The electronic control system and system software are described. (author)
Future Trends in Process Automation

OpenAIRE

Jämsä-Jounela, Sirkka-Liisa

2007-01-01

The importance of automation in the process industries has increased dramatically in recent years. In the highly industrialized countries, process automation serves to enhance product quality, master the whole range of products, improve process safety and plant availability, efficiently utilize resources and lower emissions. In the rapidly developing countries, mass production is the main motivation for applying process automation. The greatest demand for process automation is in the chemical...
Levels of automation and user control - evaluation of a turbine automation interface

Energy Technology Data Exchange (ETDEWEB)

Andersson, Jonas (Chalmers Univ. of Technology (Sweden))

2008-10-15

The study was performed during the annual operator training at the Studsvik nuclear power plant simulator facility in Nykoeping, Sweden. The participating operators came from the Oskarshamn 3 nuclear power plant. In the study, seven nuclear power plant turbine operators were interviewed concerning their use of the automatic turbine system. A field study approach together with a heuristic usability evaluation was made to assess how the operators are affected by use of automation in the control room setting. The purpose of the study was to examine how operator performance is affected by varying levels of automation in nuclear power plant turbine operation. The Automatic Turbine System (ATS) was evaluated to clarify how the ATS interface design supports the operators work. The results show that during manual control the operators experience loss of speed and accuracy in performing actions together with difficulty of dividing attention between performing a task and overall monitoring, as the major problems. The positive aspects of manual operations lie in increased feeling of being in control when performing actions by hand. With higher levels of automation the problems shift to issues concerning difficulty of following the automatic sequences and loosing track in procedures. As the level of automation gets higher, the need of feedback increases which means that information presentation also becomes more important. The use of the semiautomatic, step-mode is often preferred by the operators since it combines the speed and accuracy of the automation with the ability of maintaining the feeling of being in control. Further, a number of usability related concerns was found in the ATS interface. The operators especially experience the presentation of the conditions that manage the automatic sequences as difficult to perceive. (author)
Levels of automation and user control - evaluation of a turbine automation interface

International Nuclear Information System (INIS)

Andersson, Jonas

2008-10-01

The study was performed during the annual operator training at the Studsvik nuclear power plant simulator facility in Nykoeping, Sweden. The participating operators came from the Oskarshamn 3 nuclear power plant. In the study, seven nuclear power plant turbine operators were interviewed concerning their use of the automatic turbine system. A field study approach together with a heuristic usability evaluation was made to assess how the operators are affected by use of automation in the control room setting. The purpose of the study was to examine how operator performance is affected by varying levels of automation in nuclear power plant turbine operation. The Automatic Turbine System (ATS) was evaluated to clarify how the ATS interface design supports the operators work. The results show that during manual control the operators experience loss of speed and accuracy in performing actions together with difficulty of dividing attention between performing a task and overall monitoring, as the major problems. The positive aspects of manual operations lie in increased feeling of being in control when performing actions by hand. With higher levels of automation the problems shift to issues concerning difficulty of following the automatic sequences and loosing track in procedures. As the level of automation gets higher, the need of feedback increases which means that information presentation also becomes more important. The use of the semiautomatic, step-mode is often preferred by the operators since it combines the speed and accuracy of the automation with the ability of maintaining the feeling of being in control. Further, a number of usability related concerns was found in the ATS interface. The operators especially experience the presentation of the conditions that manage the automatic sequences as difficult to perceive. (au)
Nuclear Education and Training at Tsinghua University to Meet the Need of the Rapidly Developing Industry

International Nuclear Information System (INIS)

Sun, Y.; Han, Y.; Liu, F.

2016-01-01

Full text: The Chinese nuclear industry has been expanding rapidly since recent years. Education of highly qualified people with various educational background is an important factor for the efficient and healthy operation of the industry. Tsinghua University is offering various degree programmes for a variety of disciplines including nuclear science, nuclear engineering, nuclear safety, nuclear fuel cycle, nuclear waste treatment, energy policy and management. Degree programmes have been designed and implemented for regular school students who do not have working experience and for people who are already in their career development to better meet the requirement of the rapidly developing nuclear industry. Emphasis has also been given to the internationalization of the education programs. In addition, training programmes on a more practical basis are offered to meet specific purposes. These efforts are briefly described in this paper. (author
Automation system for optical counting of nuclear tracks

Energy Technology Data Exchange (ETDEWEB)

Boulyga, S.F.; Boulyga, E.G.; Lomonosova, E.M.; Zhuk, I.V

1999-06-01

An automation system consisting of the microscope, video camera and Pentium PC with frame recorder was created. The system provides counting of nuclear tracks on the SSNTD surface with a resolution of 752 x 582 points, determination of the surface area and main axis of the track. The pattern recognition program was developed for operation in Windows 3.1 (or higher) ensuring a convenient interface with the user. In a comparison of the results on automatic track counting with the more accurate hand mode it was shown that the program enables the tracks to be detected even on images with a rather high noise level. It ensures a high accuracy of track counting being comparable with the accuracy of manual counting for densities of tracks in the range of up to 2{center_dot}10{sup 5} tracks/cm{sup 2}. The automatic system was applied in the experimental investigation of uranium and transuranium elements.
Automation system for optical counting of nuclear tracks

International Nuclear Information System (INIS)

Boulyga, S.F.; Boulyga, E.G.; Lomonosova, E.M.; Zhuk, I.V.

1999-01-01

An automation system consisting of the microscope, video camera and Pentium PC with frame recorder was created. The system provides counting of nuclear tracks on the SSNTD surface with a resolution of 752 x 582 points, determination of the surface area and main axis of the track. The pattern recognition program was developed for operation in Windows 3.1 (or higher) ensuring a convenient interface with the user. In a comparison of the results on automatic track counting with the more accurate hand mode it was shown that the program enables the tracks to be detected even on images with a rather high noise level. It ensures a high accuracy of track counting being comparable with the accuracy of manual counting for densities of tracks in the range of up to 2·10 5 tracks/cm 2 . The automatic system was applied in the experimental investigation of uranium and transuranium elements
Automation system for optical counting of nuclear tracks

CERN Document Server

Boulyga, S F; Lomonosova, E M; Zhuk, I V

1999-01-01

An automation system consisting of the microscope, video camera and Pentium PC with frame recorder was created. The system provides counting of nuclear tracks on the SSNTD surface with a resolution of 752 x 582 points, determination of the surface area and main axis of the track. The pattern recognition program was developed for operation in Windows 3.1 (or higher) ensuring a convenient interface with the user. In a comparison of the results on automatic track counting with the more accurate hand mode it was shown that the program enables the tracks to be detected even on images with a rather high noise level. It ensures a high accuracy of track counting being comparable with the accuracy of manual counting for densities of tracks in the range of up to 2 centre dot 10 sup 5 tracks/cm sup 2. The automatic system was applied in the experimental investigation of uranium and transuranium elements.
Semi-automated, occupationally safe immunofluorescence microtip sensor for rapid detection of Mycobacterium cells in sputum.

Directory of Open Access Journals (Sweden)

Shinnosuke Inoue

Full Text Available An occupationally safe (biosafe sputum liquefaction protocol was developed for use with a semi-automated antibody-based microtip immunofluorescence sensor. The protocol effectively liquefied sputum and inactivated microorganisms including Mycobacterium tuberculosis, while preserving the antibody-binding activity of Mycobacterium cell surface antigens. Sputum was treated with a synergistic chemical-thermal protocol that included moderate concentrations of NaOH and detergent at 60°C for 5 to 10 min. Samples spiked with M. tuberculosis complex cells showed approximately 10(6-fold inactivation of the pathogen after treatment. Antibody binding was retained post-treatment, as determined by analysis with a microtip immunosensor. The sensor correctly distinguished between Mycobacterium species and other cell types naturally present in biosafe-treated sputum, with a detection limit of 100 CFU/mL for M. tuberculosis, in a 30-minute sample-to-result process. The microtip device was also semi-automated and shown to be compatible with low-cost, LED-powered fluorescence microscopy. The device and biosafe sputum liquefaction method opens the door to rapid detection of tuberculosis in settings with limited laboratory infrastructure.
Automated system of control of radioactive liquid effluents of patients submitted to therapy in hospitals of nuclear medicine (SACEL)

International Nuclear Information System (INIS)

Ruiz C, M.A.; Rivero G, T.; Celis del Angel, L.; Sainz M, E.; Molina, G.

2006-01-01

Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote
Automated TIG welding system with visual sensor for repairing nuclear plants

International Nuclear Information System (INIS)

Inoue, Katsunori; Watanabe, Hiroshi; Kondoh, Yoshihide.

1986-01-01

An automated TIG welding system has been developed. This system is to be used for repairing nuclear plants, whose work environment is highly radioactive, so should have the automatic self control function and the remote controllable function. For this purpose, the visual sensor, a TV camera and an image processor, is installed and the image processing technique is applied to the all-position TIG welding system. In this system, all controls are made with microprocessors and every necessary information is displayed on the screen of the remote control unit. The excellent performance was obtained as the application of this system to the practical field. (author)
Automated track recognition and event reconstruction in nuclear emulsion

International Nuclear Information System (INIS)

Deines-Jones, P.; Aranas, A.; Cherry, M.L.; Dugas, J.; Kudzia, D.; Nilsen, B.S.; Sengupta, K.; Waddington, C.J.; Wefel, J.P.; Wilczynska, B.; Wilczynski, H.; Wosiek, B.

1997-01-01

The major advantages of nuclear emulsion for detecting charged particles are its submicron position resolution and sensitivity to minimum ionizing particles. These must be balanced, however, against the difficult manual microscope measurement by skilled observers required for the analysis. We have developed an automated system to acquire and analyze the microscope images from emulsion chambers. Each emulsion plate is analyzed independently, allowing coincidence techniques to be used in order to reject background and estimate error rates. The system has been used to analyze a sample of high-multiplicity Pb-Pb interactions (charged particle multiplicities ∝ 1100) produced by the 158 GeV/c per nucleon 208 Pb beam at CERN. Automatically measured events agree with our best manual measurements on 97% of all the tracks. We describe the image analysis and track reconstruction techniques, and discuss the measurement and reconstruction uncertainties. (orig.)
Description and Methods of the Automated Document Management System Usage in Scientific Organizational Activities of the Joint Institute for Nuclear Research (ADS SOA JINR)

CERN Document Server

Borisovsky, V F; Kekelidze, M G; Nikonov, E G; Senchenko, V A

2005-01-01

This paper presents the structure description and user guide for Information program system for automation of a document flow for support of scientific arrangement planning (ADS SOA) which can be used for planning and carrying out seminars, workshops, conferences and other arrangements of research management. This work is intended for automation of scientific research management in the Joint Institute for Nuclear Research. The complex of programs represents the CDS Agenda system used in the European Organization for Nuclear Research (CERN), which is adapted to the conditions of JINR.
Rapid Radiochemical Analyses in Support of Fukushima Nuclear Accident - 13196

Energy Technology Data Exchange (ETDEWEB)

Maxwell, Sherrod L.; Culligan, Brian K.; Hutchison, Jay B. [Savannah River National Laboratory, Building 735-B, Aiken, SC 29808 (United States)

2013-07-01

There is an increasing need to develop faster analytical methods for emergency response, including emergency soil and air filter samples [1, 2]. The Savannah River National Laboratory (SRNL) performed analyses on samples received from Japan in April, 2011 as part of a U.S. Department of Energy effort to provide assistance to the government of Japan, following the nuclear event at Fukushima Daiichi, resulting from the earthquake and tsunami on March 11, 2011. Of particular concern was whether it was safe to plant rice in certain areas (prefectures) near Fukushima. The primary objectives of the sample collection, sample analysis, and data assessment teams were to evaluate personnel exposure hazards, identify the nuclear power plant radiological source term and plume deposition, and assist the government of Japan in assessing any environmental and agricultural impacts associated with the nuclear event. SRNL analyzed approximately 250 samples and reported approximately 500 analytical method determinations. Samples included soil from farmland surrounding the Fukushima reactors and air monitoring samples of national interest, including those collected at the U.S. Embassy and American military bases. Samples were analyzed for a wide range of radionuclides, including strontium-89, strontium-90, gamma-emitting radionuclides, and plutonium, uranium, americium and curium isotopes. Technical aspects of the rapid soil and air filter analyses will be described. The extent of radiostrontium contamination was a significant concern. For {sup 89,90}Sr analyses on soil samples, a rapid fusion technique using 1.5 gram soil aliquots to enable a Minimum Detectable Activity (MDA) of <1 pCi {sup 89,90}Sr /g of soil was employed. This sequential technique has been published recently by this laboratory for actinides and radiostrontium in soil and vegetation [3, 4]. It consists of a rapid sodium hydroxide fusion, pre-concentration steps using iron hydroxide and calcium fluoride
Automated Tracking of Cell Migration with Rapid Data Analysis.

Science.gov (United States)

DuChez, Brian J

2017-09-01

Cell migration is essential for many biological processes including development, wound healing, and metastasis. However, studying cell migration often requires the time-consuming and labor-intensive task of manually tracking cells. To accelerate the task of obtaining coordinate positions of migrating cells, we have developed a graphical user interface (GUI) capable of automating the tracking of fluorescently labeled nuclei. This GUI provides an intuitive user interface that makes automated tracking accessible to researchers with no image-processing experience or familiarity with particle-tracking approaches. Using this GUI, users can interactively determine a minimum of four parameters to identify fluorescently labeled cells and automate acquisition of cell trajectories. Additional features allow for batch processing of numerous time-lapse images, curation of unwanted tracks, and subsequent statistical analysis of tracked cells. Statistical outputs allow users to evaluate migratory phenotypes, including cell speed, distance, displacement, and persistence, as well as measures of directional movement, such as forward migration index (FMI) and angular displacement. © 2017 by John Wiley & Sons, Inc. Copyright © 2017 John Wiley & Sons, Inc.
An automatic injection system for rapid radiochemistry

International Nuclear Information System (INIS)

Nurmia, M.J.; Kreek, S.A.; Kadkhodayan, B.; Gregorich, K.E.; Lee, D.M.; Hoffman, D.C.

1992-01-01

A description is given of the Automated Injection System (AIS), a pneumatically actuated device for automated collection of nuclear reaction products from a He/KCl gas jet transport system. The AIS is used with the Automated Chemical Chromatographic Element Separation System; together these two devices facilitate completely automated separation procedures with improved speed and reproducibility
A rapid and continuous system for immobilization of nuclear material waste by vitrification

International Nuclear Information System (INIS)

Shareef, M.U.; Hussain, S.H.; Tufail, M.; Rashid, F.

2009-01-01

The nuclear technology has prime importance and backbone for rapid development of medical sciences, industries and in power generation as an alternate source of energy. Despite all these facts there is a major problem which is always associated with nuclear technology, that is, the generation of undesirable radioactive wastes. The radioactive wastes are quite problematic and need major attention for its treatment, conditioning and properly disposal to keep the environmental activities and human ecosystem healthy and safe. There are different large scale methods and processes to treat and dispose off the radioactive wastes. These processes are evaluated and designed by the various world competent and pronounced scientists in the light of rules and safety limits set by IAEA and other regulatory authorities to protect the environment and eventually protect our ecosystem. The research and development work on radioactive waste has been proceeding for the last fifty years but still it is a core issue and a big challenge for the nuclear scientists and radiation workers. In this study a rapid and continuous system for immobilization of nuclear waste into glass matrix by vitrification has been designed. In general treatment methods, Borosilicate glass is preferred because it is efficient, cost effective and rapid to that of other radioactive waste form. In this process the simulated waste is mixed with glass forming material and process for melting to form a glassy substrate in continuous manner. The waste is being converted into vitreous form and encapsulate into a glass matrix. (author)

Development of a Multi-Channel Ultrasonic Testing System for Automated Ultrasonic Pipe Inspection of Nuclear Power Plant

International Nuclear Information System (INIS)

Lee, Hee Jong; Cho, Chan Hee; Cho, Hyun Joon

2009-01-01

Currently almost all in-service-inspection techniques, applied in domestic nuclear power plants, are partial to field inspection technique. These kinds of techniques are related to managing nuclear power plants by the operation of foreign-produced inspection devices. There have been so many needs for development of native in-service-inspection device because there is no native diagnosis device for nuclear power plant inspection yet in Korea. In this research, we developed several core techniques to make an automated ultrasonic pipe inspection system for nuclear power plants. A high performance multi-channel ultrasonic pulser/receiver module, an A/D converter module and a digital main CPU module were developed and the performance of the developed modules was verified. The S/N ratio, noise level and signal acquisition performance of the developed modules showed proper level as we designed in the beginning.
From SRAFAP to SISAK - rapid chemical separations in nuclear research

International Nuclear Information System (INIS)

Herrmann, G.

1988-10-01

The author gives an overview of rapid radiochemical separations, starting from the early experiments done by Rutherford up to the very sophisticated recoil fragment separations by fast on-line methods as an attempt to produce superheavy elements. Main emphasis is given to developments during the last decades and the extensive work performed by collaborators of the Nuclear Chemistry Institute at the University of Mainz. (RB)
Automated local bright feature image analysis of nuclear proteindistribution identifies changes in tissue phenotype

Energy Technology Data Exchange (ETDEWEB)

Knowles, David; Sudar, Damir; Bator, Carol; Bissell, Mina

2006-02-01

The organization of nuclear proteins is linked to cell and tissue phenotypes. When cells arrest proliferation, undergo apoptosis, or differentiate, the distribution of nuclear proteins changes. Conversely, forced alteration of the distribution of nuclear proteins modifies cell phenotype. Immunostaining and fluorescence microscopy have been critical for such findings. However, there is an increasing need for quantitative analysis of nuclear protein distribution to decipher epigenetic relationships between nuclear structure and cell phenotype, and to unravel the mechanisms linking nuclear structure and function. We have developed imaging methods to quantify the distribution of fluorescently-stained nuclear protein NuMA in different mammary phenotypes obtained using three-dimensional cell culture. Automated image segmentation of DAPI-stained nuclei was generated to isolate thousands of nuclei from three-dimensional confocal images. Prominent features of fluorescently-stained NuMA were detected using a novel local bright feature analysis technique, and their normalized spatial density calculated as a function of the distance from the nuclear perimeter to its center. The results revealed marked changes in the distribution of the density of NuMA bright features as non-neoplastic cells underwent phenotypically normal acinar morphogenesis. In contrast, we did not detect any reorganization of NuMA during the formation of tumor nodules by malignant cells. Importantly, the analysis also discriminated proliferating non-neoplastic cells from proliferating malignant cells, suggesting that these imaging methods are capable of identifying alterations linked not only to the proliferation status but also to the malignant character of cells. We believe that this quantitative analysis will have additional applications for classifying normal and pathological tissues.
Automation in Immunohematology

Directory of Open Access Journals (Sweden)

Meenu Bajpai

2012-01-01

Full Text Available There have been rapid technological advances in blood banking in South Asian region over the past decade with an increasing emphasis on quality and safety of blood products. The conventional test tube technique has given way to newer techniques such as column agglutination technique, solid phase red cell adherence assay, and erythrocyte-magnetized technique. These new technologies are adaptable to automation and major manufacturers in this field have come up with semi and fully automated equipments for immunohematology tests in the blood bank. Automation improves the objectivity and reproducibility of tests. It reduces human errors in patient identification and transcription errors. Documentation and traceability of tests, reagents and processes and archiving of results is another major advantage of automation. Shifting from manual methods to automation is a major undertaking for any transfusion service to provide quality patient care with lesser turnaround time for their ever increasing workload. This article discusses the various issues involved in the process.
Rapid Automated Dissolution and Analysis Techniques for Radionuclides in Recycle Process Streams

International Nuclear Information System (INIS)

Sudowe, Ralf; Roman, Audrey; Dailey, Ashlee; Go, Elaine

2013-01-01

The analysis of process samples for radionuclide content is an important part of current procedures for material balance and accountancy in the different process streams of a recycling plant. The destructive sample analysis techniques currently available necessitate a significant amount of time. It is therefore desirable to develop new sample analysis procedures that allow for a quick turnaround time and increased sample throughput with a minimum of deviation between samples. In particular, new capabilities for rapid sample dissolution and radiochemical separation are required. Most of the radioanalytical techniques currently employed for sample analysis are based on manual laboratory procedures. Such procedures are time- and labor-intensive, and not well suited for situations in which a rapid sample analysis is required and/or large number of samples need to be analyzed. To address this issue we are currently investigating radiochemical separation methods based on extraction chromatography that have been specifically optimized for the analysis of process stream samples. The influence of potential interferences present in the process samples as well as mass loading, flow rate and resin performance is being studied. In addition, the potential to automate these procedures utilizing a robotic platform is evaluated. Initial studies have been carried out using the commercially available DGA resin. This resin shows an affinity for Am, Pu, U, and Th and is also exhibiting signs of a possible synergistic effects in the presence of iron.
Optimization of automation: II. Estimation method of ostracism rate based on the loss of situation awareness of human operators in nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Min; Kim, Man Cheol; Kim, Jong Hyun; Seong, Poong Hyun

2015-01-01

Highlights: • We analyze the relationship between Out-of-the-Loop and the loss of human operators’ situation awareness. • We propose an ostracism rate estimation method by only considering the negative effects of automation. • The ostracism rate reflects how much automation interrupts human operators to receive information. • The higher the ostracism rate is, the lower the accuracy of human operators’ SA will be. - Abstract: With the introduction of automation in various industries including the nuclear field, its side effect, referred to as the Out-of-the-Loop (OOTL) problem, has emerged as a critical issue that needs to be addressed. Many studies have been attempted to analyze and solve the OOTL problem, but this issue still needs a clear solution to provide criteria for introducing automation. Therefore, a quantitative estimation method for identifying negative effects of automation is proposed in this paper. The representative aspect of the OOTL problem in nuclear power plants (NPPs) is that human operators in automated operations are given less information than human operators in manual operations. In other words, human operators have less opportunity to obtain needed information as automation is introduced. From this point of view, the degree of difficulty in obtaining information from automated systems is defined as the Level of Ostracism (LOO). Using the LOO and information theory, we propose the ostracism rate, which is a new estimation method that expresses how much automation interrupts human operators’ situation awareness. We applied production rules to describe the human operators’ thinking processes, Bayesian inference to describe the production rules mathematically, and information theory to calculate the amount of information that human operators receive through observations. The validity of the suggested method was proven by conducting an experiment. The results show that the ostracism rate was significantly related to the accuracy
Automated Processing and Evaluation of Anti-Nuclear Antibody Indirect Immunofluorescence Testing.

Science.gov (United States)

Ricchiuti, Vincent; Adams, Joseph; Hardy, Donna J; Katayev, Alexander; Fleming, James K

2018-01-01

Indirect immunofluorescence (IIF) is considered by the American College of Rheumatology (ACR) and the international consensus on ANA patterns (ICAP) the gold standard for the screening of anti-nuclear antibodies (ANA). As conventional IIF is labor intensive, time-consuming, subjective, and poorly standardized, there have been ongoing efforts to improve the standardization of reagents and to develop automated platforms for assay incubation, microscopy, and evaluation. In this study, the workflow and performance characteristics of a fully automated ANA IIF system (Sprinter XL, EUROPattern Suite, IFA 40: HEp-20-10 cells) were compared to a manual approach using visual microscopy with a filter device for single-well titration and to technologist reading. The Sprinter/EUROPattern system enabled the processing of large daily workload cohorts in less than 8 h and the reduction of labor hands-on time by more than 4 h. Regarding the discrimination of positive from negative samples, the overall agreement of the EUROPattern software with technologist reading was higher (95.6%) than when compared to the current method (89.4%). Moreover, the software was consistent with technologist reading in 80.6-97.5% of patterns and 71.0-93.8% of titers. In conclusion, the Sprinter/EUROPattern system provides substantial labor savings and good concordance with technologist ANA IIF microscopy, thus increasing standardization, laboratory efficiency, and removing subjectivity.
Automated Processing and Evaluation of Anti-Nuclear Antibody Indirect Immunofluorescence Testing

Directory of Open Access Journals (Sweden)

Vincent Ricchiuti

2018-05-01

Full Text Available Indirect immunofluorescence (IIF is considered by the American College of Rheumatology (ACR and the international consensus on ANA patterns (ICAP the gold standard for the screening of anti-nuclear antibodies (ANA. As conventional IIF is labor intensive, time-consuming, subjective, and poorly standardized, there have been ongoing efforts to improve the standardization of reagents and to develop automated platforms for assay incubation, microscopy, and evaluation. In this study, the workflow and performance characteristics of a fully automated ANA IIF system (Sprinter XL, EUROPattern Suite, IFA 40: HEp-20-10 cells were compared to a manual approach using visual microscopy with a filter device for single-well titration and to technologist reading. The Sprinter/EUROPattern system enabled the processing of large daily workload cohorts in less than 8 h and the reduction of labor hands-on time by more than 4 h. Regarding the discrimination of positive from negative samples, the overall agreement of the EUROPattern software with technologist reading was higher (95.6% than when compared to the current method (89.4%. Moreover, the software was consistent with technologist reading in 80.6–97.5% of patterns and 71.0–93.8% of titers. In conclusion, the Sprinter/EUROPattern system provides substantial labor savings and good concordance with technologist ANA IIF microscopy, thus increasing standardization, laboratory efficiency, and removing subjectivity.
A novel automated device for rapid nucleic acid extraction utilizing a zigzag motion of magnetic silica beads

International Nuclear Information System (INIS)

Yamaguchi, Akemi; Matsuda, Kazuyuki; Uehara, Masayuki; Honda, Takayuki; Saito, Yasunori

2016-01-01

We report a novel automated device for nucleic acid extraction, which consists of a mechanical control system and a disposable cassette. The cassette is composed of a bottle, a capillary tube, and a chamber. After sample injection in the bottle, the sample is lysed, and nucleic acids are adsorbed on the surface of magnetic silica beads. These magnetic beads are transported and are vibrated through the washing reagents in the capillary tube under the control of the mechanical control system, and thus, the nucleic acid is purified without centrifugation. The purified nucleic acid is automatically extracted in 3 min for the polymerase chain reaction (PCR). The nucleic acid extraction is dependent on the transport speed and the vibration frequency of the magnetic beads, and optimizing these two parameters provided better PCR efficiency than the conventional manual procedure. There was no difference between the detection limits of our novel device and that of the conventional manual procedure. We have already developed the droplet-PCR machine, which can amplify and detect specific nucleic acids rapidly and automatically. Connecting the droplet-PCR machine to our novel automated extraction device enables PCR analysis within 15 min, and this system can be made available as a point-of-care testing in clinics as well as general hospitals. - Highlights: • Automatic nucleic acid extraction is performed in 3 min. • Zigzag motion of magnetic silica beads yields rapid and efficient extraction. • The present our device provides better performance than the conventional procedure.
Rapid nuclear forensics analysis via laser based microphotonic techniques coupled with chemometrics

International Nuclear Information System (INIS)

Bhatta, B.; Kalambuka, H.A.; Dehayem-Kamadjeu, A.

2017-01-01

Nuclear forensics (NF) is an important tool for analysis and attribution of nuclear and radiological materials (NRM) in support of nuclear security. The critical challenge in NF currently is the lack of suitable microanalytical methodologies for direct, rapid and minimally-invasive detection and quantification of NF signatures. Microphotonic techniques can achieve this task particularly when the materials are of limited size and under concealed condition. The purpose of this paper is to demonstrate the combined potential of chemometrics enabled LIBS and laser Raman spectromicroscopy (LRS) for rapid NF analysis and attribution. Using LIBS, uranium lines at 385.464 nm, 385.957 nm and 386.592 nm were identified as NF signatures in uranium ore surrogates. A multivariate calibration strategy using artificial neural network was developed for quantification of trace uranium. Principal component analysis (PCA) of LIBS spectra achieved source attribution of the ores. LRS studies on UCl3, UO3(NO3)2.6H2O, UO2SO4.3H2O and UO3 in pellet state identified the bands associated with different uranium molecules as varying in the range of (840 to 867) ± 15 cm-1. Using this signature, we have demonstrated spectral imaging of uranium under concealed conditions (author)
The impact of automation on operator performance. An explorative study

International Nuclear Information System (INIS)

Tasset, Daniel; Charron, Sylvie; Miberg, Ann-Britt; Hollnagel, Erik

1999-01-01

This study addresses the issue of human-automation interaction in nuclear power plant control rooms. It was initiated by the Institut de Protection et de Surete Nucleaire (IPSN - France) in 1996, and has been carried out in a co-operation between the Institutt for Energiteknikk (IFE) and IPSN, 1996-1998. The purpose of the study is to contribute to the understanding of how automatic systems affect operator performance in nuclear power plants. The results of the project will be used in two ways. First, they will support the identification of particular human-automation issues of interest for future human-automation studies. Second, they will be used by IPSN to initiate the development of a knowledge-based aimed at supporting the conduction of comparative analyses between different human-automation set-ups in French nuclear power plants (author) (ml)
Human-centered automation of testing, surveillance and maintenance

International Nuclear Information System (INIS)

Bhatt, S.C.; Sun, B.K.H.

1991-01-01

Manual surveillance and testing of instrumentation, control and protection systems at nuclear power plants involves system and human errors which can lead to substantial plant down time. Frequent manual testing can also contribute significantly to operation and maintenance cost. Automation technology offers potential for prudent applications at the power plant to reduce testing errors and cost. To help address the testing problems and to harness the benefit of automation application, input from utilities is obtained on suitable automation approaches. This paper includes lessens from successful past experience at a few plants where some island of automation exist. The results are summarized as a set of specifications for semi automatic testing. A human-centered automation methodology is proposed with the guidelines for optimal human/computer division of tasks given. Implementation obstacles for significant changes of testing practices are identified and methods acceptable to nuclear power plants for addressing these obstacles have been suggested
Automated radioxenon monitoring for the comprehensive nuclear-test-ban treaty in two distinctive locations: Ottawa and Tahiti

International Nuclear Information System (INIS)

Stocki, T.J.; Blanchard, X.; D'Amours, R.; Ungar, R.K.; Fontaine, J.P.; Sohier, M.; Bean, M.; Taffary, T.; Racine, J.; Tracy, B.L.; Brachet, G.; Jean, M.; Meyerhof, D.

2005-01-01

In preparation for verification of the Comprehensive Nuclear-Test-Ban-Treaty, automated radioxenon monitoring is performed in two distinctive environments: Ottawa and Tahiti. These sites are monitored with SPALAX (Systeme de Prelevement d'air Automatique en Ligne avec l'Analyse des radioXenons) technology, which automatically extracts radioxenon from the atmosphere and measures the activity concentrations of 131m,133m,133,135 Xe. The resulting isotopic concentrations can be useful to discern nuclear explosions from nuclear industry xenon emissions. Ambient radon background, which may adversely impact analyser sensitivity, is discussed. Upper concentration limits are reported for the apparently radioxenon free Tahiti environment. Ottawa has a complex radioxenon background due to proximity to nuclear reactors and medical isotope facilities. Meteorological models suggest that, depending on the wind direction, the radioxenon detected in Ottawa can be characteristic of the normal radioxenon background in the Eastern United States, Europe, and Japan or distinctive due to medical isotope production
Automated radioxenon monitoring for the comprehensive nuclear-test-ban treaty in two distinctive locations: Ottawa and Tahiti.

Science.gov (United States)

Stocki, T J; Blanchard, X; D'Amours, R; Ungar, R K; Fontaine, J P; Sohier, M; Bean, M; Taffary, T; Racine, J; Tracy, B L; Brachet, G; Jean, M; Meyerhof, D

2005-01-01

In preparation for verification of the Comprehensive Nuclear-Test-Ban-Treaty, automated radioxenon monitoring is performed in two distinctive environments: Ottawa and Tahiti. These sites are monitored with SPALAX (Systeme de Prelevement d'air Automatique en Ligne avec l'Analyse des radioXenons) technology, which automatically extracts radioxenon from the atmosphere and measures the activity concentrations of (131m,133m,133,135)Xe. The resulting isotopic concentrations can be useful to discern nuclear explosions from nuclear industry xenon emissions. Ambient radon background, which may adversely impact analyser sensitivity, is discussed. Upper concentration limits are reported for the apparently radioxenon free Tahiti environment. Ottawa has a complex radioxenon background due to proximity to nuclear reactors and medical isotope facilities. Meteorological models suggest that, depending on the wind direction, the radioxenon detected in Ottawa can be characteristic of the normal radioxenon background in the Eastern United States, Europe, and Japan or distinctive due to medical isotope production.
Ecological Automation Design, Extending Work Domain Analysis

NARCIS (Netherlands)

Amelink, M.H.J.

2010-01-01

In high–risk domains like aviation, medicine and nuclear power plant control, automation has enabled new capabilities, increased the economy of operation and has greatly contributed to safety. However, automation increases the number of couplings in a system, which can inadvertently lead to more
Automated analysis of connected speech reveals early biomarkers of Parkinson's disease in patients with rapid eye movement sleep behaviour disorder.

Science.gov (United States)

Hlavnička, Jan; Čmejla, Roman; Tykalová, Tereza; Šonka, Karel; Růžička, Evžen; Rusz, Jan

2017-02-02

For generations, the evaluation of speech abnormalities in neurodegenerative disorders such as Parkinson's disease (PD) has been limited to perceptual tests or user-controlled laboratory analysis based upon rather small samples of human vocalizations. Our study introduces a fully automated method that yields significant features related to respiratory deficits, dysphonia, imprecise articulation and dysrhythmia from acoustic microphone data of natural connected speech for predicting early and distinctive patterns of neurodegeneration. We compared speech recordings of 50 subjects with rapid eye movement sleep behaviour disorder (RBD), 30 newly diagnosed, untreated PD patients and 50 healthy controls, and showed that subliminal parkinsonian speech deficits can be reliably captured even in RBD patients, which are at high risk of developing PD or other synucleinopathies. Thus, automated vocal analysis should soon be able to contribute to screening and diagnostic procedures for prodromal parkinsonian neurodegeneration in natural environments.
Development of automated operating procedure system using fuzzy colored petri nets for nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Jun; Seong, Poong Hyun

2004-01-01

In this work, AuTomated Operating Procedure System (ATOPS) is developed. ATOPS is an automation system for emergency operation of a nuclear power plant (NPP) and it can monitor signals, diagnose statuses, and generate control actions according to corresponding operating procedures without any human operator's help. Main functions of ATOPS are an anomaly detection function and a procedure execution function but only the procedure execution function is implemented in this work because this work is just the first step. In the procedure execution function, operating procedures of NPPs are analyzed and modeled using Fuzzy Colored Petri Nets (FCPN) and executed depending on decision making of the inference engine. In this work, ATOPS prototype is developed to demonstrate its feasibility and it is also validated using the FISA-2/WS simulator. The validation is performed for the cases of a loss of coolant accident (LOCA) and a steam generator tube rupture (SGTR). The simulation results show that ATOPS works correctly in the emergency situations
Automated local bright feature image analysis of nuclear protein distribution identifies changes in tissue phenotype

International Nuclear Information System (INIS)

Knowles, David; Sudar, Damir; Bator, Carol; Bissell, Mina

2006-01-01

The organization of nuclear proteins is linked to cell and tissue phenotypes. When cells arrest proliferation, undergo apoptosis, or differentiate, the distribution of nuclear proteins changes. Conversely, forced alteration of the distribution of nuclear proteins modifies cell phenotype. Immunostaining and fluorescence microscopy have been critical for such findings. However, there is an increasing need for quantitative analysis of nuclear protein distribution to decipher epigenetic relationships between nuclear structure and cell phenotype, and to unravel the mechanisms linking nuclear structure and function. We have developed imaging methods to quantify the distribution of fluorescently-stained nuclear protein NuMA in different mammary phenotypes obtained using three-dimensional cell culture. Automated image segmentation of DAPI-stained nuclei was generated to isolate thousands of nuclei from three-dimensional confocal images. Prominent features of fluorescently-stained NuMA were detected using a novel local bright feature analysis technique, and their normalized spatial density calculated as a function of the distance from the nuclear perimeter to its center. The results revealed marked changes in the distribution of the density of NuMA bright features as non-neoplastic cells underwent phenotypically normal acinar morphogenesis. In contrast, we did not detect any reorganization of NuMA during the formation of tumor nodules by malignant cells. Importantly, the analysis also discriminated proliferating non-neoplastic cells from proliferating malignant cells, suggesting that these imaging methods are capable of identifying alterations linked not only to the proliferation status but also to the malignant character of cells. We believe that this quantitative analysis will have additional applications for classifying normal and pathological tissues
Layered distributed architecture for plant automation

International Nuclear Information System (INIS)

Aravamuthan, G.; Verma, Yachika; Ranjan, Jyoti; Chachondia, Alka S.; Ganesh, G.

2005-01-01

The development of plant automation system and associated software remains one of the greatest challenges to the widespread implementation of highly adaptive re-configurable automation technology. This paper presents a layered distributed architecture for a plant automation system designed to support rapid reconfiguration and redeployment of automation components. The paper first presents evolution of automation architecture and their associated environment in the past few decades and then presents the concept of layered system architecture and the use of automation components to support the construction of a wide variety of automation system. It also highlights the role of standards and technology, which can be used in the development of automation components. We have attempted to adhere to open standards and technology for the development of automation component at a various layers. It also highlights the application of this concept in the development of an Operator Information System (OIS) for Advanced Heavy Water Reactor (AHWR). (author)
Automation in a material processing/storage facility

International Nuclear Information System (INIS)

Peterson, K.; Gordon, J.

1997-01-01

The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, therefore, be accomplished in a rational and disciplined manner to satisfy the strict operational requirements of the facility. Among the functions to be automated are the transport of containers between process and storage areas via an Automatic Guided Vehicle (AGV), and various processes in the Shipping Package Unpackaging (SPU) area, the Accountability Measurements (AM) area, the Special Isotope Storage (SIS) vault and the Special Nuclear Materials (SNM) vault. Other areas of the facility are also being automated, but are outside the scope of this paper

Automation of orders in taxi service

OpenAIRE

Simčič, Matej

2012-01-01

Automation is rapidly growing in the last years. The advantages it brings are cost reduction, faster and better performance of tasks that would be otherwise done by humas. It began in the manufacturing industry and later expanded to other sectors. Today's technology allows the implementation of automation in a wide range of areas. The thesis deals with the implementation of a system that allows automated ordering of a taxi. The system consists of four components. They are two mobile app...
ROBOCAL: An automated NDA [nondestructive analysis] calorimetry and gamma isotopic system

International Nuclear Information System (INIS)

Hurd, J.R.; Powell, W.D.; Ostenak, C.A.

1989-01-01

ROBOCAL, which is presently being developed and tested at Los Alamos National Laboratory, is a full-scale, prototype robotic system for remote calorimetric and gamma-ray analysis of special nuclear materials. It integrates a fully automated, multidrawer, vertical stacker-retriever system for staging unmeasured nuclear materials, and a fully automated gantry robot for computer-based selection and transfer of nuclear materials to calorimetric and gamma-ray measurement stations. Since ROBOCAL is designed for minimal operator intervention, a completely programmed user interface is provided to interact with the automated mechanical and assay systems. The assay system is designed to completely integrate calorimetric and gamma-ray data acquisition and to perform state-of-the-art analyses on both homogeneous and heterogeneous distributions of nuclear materials in a wide variety of matrices
Preliminary Framework for Human-Automation Collaboration

International Nuclear Information System (INIS)

Oxstrand, Johanna Helene; Le Blanc, Katya Lee; Spielman, Zachary Alexander

2015-01-01

The Department of Energy's Advanced Reactor Technologies Program sponsors research, development and deployment activities through its Next Generation Nuclear Plant, Advanced Reactor Concepts, and Advanced Small Modular Reactor (aSMR) Programs to promote safety, technical, economical, and environmental advancements of innovative Generation IV nuclear energy technologies. The Human Automation Collaboration (HAC) Research Project is located under the aSMR Program, which identifies developing advanced instrumentation and controls and human-machine interfaces as one of four key research areas. It is expected that the new nuclear power plant designs will employ technology significantly more advanced than the analog systems in the existing reactor fleet as well as utilizing automation to a greater extent. Moving towards more advanced technology and more automation does not necessary imply more efficient and safer operation of the plant. Instead, a number of concerns about how these technologies will affect human performance and the overall safety of the plant need to be addressed. More specifically, it is important to investigate how the operator and the automation work as a team to ensure effective and safe plant operation, also known as the human-automation collaboration (HAC). The focus of the HAC research is to understand how various characteristics of automation (such as its reliability, processes, and modes) effect an operator's use and awareness of plant conditions. In other words, the research team investigates how to best design the collaboration between the operators and the automated systems in a manner that has the greatest positive impact on overall plant performance and reliability. This report addresses the Department of Energy milestone M4AT-15IN2302054, Complete Preliminary Framework for Human-Automation Collaboration, by discussing the two phased development of a preliminary HAC framework. The framework developed in the first phase was used as
Preliminary Framework for Human-Automation Collaboration

Energy Technology Data Exchange (ETDEWEB)

Oxstrand, Johanna Helene [Idaho National Lab. (INL), Idaho Falls, ID (United States); Le Blanc, Katya Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary Alexander [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-09-01

The Department of Energy’s Advanced Reactor Technologies Program sponsors research, development and deployment activities through its Next Generation Nuclear Plant, Advanced Reactor Concepts, and Advanced Small Modular Reactor (aSMR) Programs to promote safety, technical, economical, and environmental advancements of innovative Generation IV nuclear energy technologies. The Human Automation Collaboration (HAC) Research Project is located under the aSMR Program, which identifies developing advanced instrumentation and controls and human-machine interfaces as one of four key research areas. It is expected that the new nuclear power plant designs will employ technology significantly more advanced than the analog systems in the existing reactor fleet as well as utilizing automation to a greater extent. Moving towards more advanced technology and more automation does not necessary imply more efficient and safer operation of the plant. Instead, a number of concerns about how these technologies will affect human performance and the overall safety of the plant need to be addressed. More specifically, it is important to investigate how the operator and the automation work as a team to ensure effective and safe plant operation, also known as the human-automation collaboration (HAC). The focus of the HAC research is to understand how various characteristics of automation (such as its reliability, processes, and modes) effect an operator’s use and awareness of plant conditions. In other words, the research team investigates how to best design the collaboration between the operators and the automated systems in a manner that has the greatest positive impact on overall plant performance and reliability. This report addresses the Department of Energy milestone M4AT-15IN2302054, Complete Preliminary Framework for Human-Automation Collaboration, by discussing the two phased development of a preliminary HAC framework. The framework developed in the first phase was used as the
Instrumentation, controls and automation in the power industry

International Nuclear Information System (INIS)

Anon.

1991-01-01

The year 1991 will be remembered as the year EPRI joined with the ISA Power Division to present an outstanding group to technical papers at the First Annual ISA/EPRI Joint Controls and Automation Conference. All papers met the theme for the conference namely Innovative Instrumentation, Controls, and Automation Techniques for the Power Generation Industry and cover a myriad of application ranging from nuclear to conventional fossil to co-generation plants involving nuclear, conventional BTG, and combined cycle equipment applications
Rapid, portable detection of endocrine disrupting chemicals through ligand-nuclear hormone receptor interactions.

Science.gov (United States)

Hunt, J Porter; Schinn, Song-Min; Jones, Matthew D; Bundy, Bradley C

2017-12-04

Endocrine disrupting chemicals (EDC) are structurally diverse compounds that can interact with nuclear hormone receptors, posing significant risk to human and ecological health. Unfortunately, many conventional biosensors have been too structure-specific, labor-intensive or laboratory-oriented to detect broad ranges of EDC effectively. Recently, several technological advances are providing more rapid, portable, and affordable detection of endocrine-disrupting activity through ligand-nuclear hormone receptor interactions. Here, we overview these recent advances applied to EDC biosensors - including cell lyophilization, cell immobilization, cell-free systems, smartphone-based signal detection, and improved competitive binding assays.
Nuclear Magnetic Resonance Spectroscopy-Based Identification of Yeast.

Science.gov (United States)

Himmelreich, Uwe; Sorrell, Tania C; Daniel, Heide-Marie

2017-01-01

Rapid and robust high-throughput identification of environmental, industrial, or clinical yeast isolates is important whenever relatively large numbers of samples need to be processed in a cost-efficient way. Nuclear magnetic resonance (NMR) spectroscopy generates complex data based on metabolite profiles, chemical composition and possibly on medium consumption, which can not only be used for the assessment of metabolic pathways but also for accurate identification of yeast down to the subspecies level. Initial results on NMR based yeast identification where comparable with conventional and DNA-based identification. Potential advantages of NMR spectroscopy in mycological laboratories include not only accurate identification but also the potential of automated sample delivery, automated analysis using computer-based methods, rapid turnaround time, high throughput, and low running costs.We describe here the sample preparation, data acquisition and analysis for NMR-based yeast identification. In addition, a roadmap for the development of classification strategies is given that will result in the acquisition of a database and analysis algorithms for yeast identification in different environments.
Automated data reduction for optical interferometric data

International Nuclear Information System (INIS)

Boyd, R.D.; Miller, D.J.; Ghiglia, D.C.

1983-01-01

The potential for significant progress in understanding many transport processes exists through the use of a rapid and automated data reduction process of optical interferometric data. An example involving natural convection in a horizontal annulus is used to demonstrate that the accuracy possible in automated techniques is better than 99.0%
Development of an automated operating procedure system using fuzzy colored petri nets for nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Jun; Seong, Poong Hyun

2002-01-01

In this work, AuTomated Operating Procedure System (ATOPS) is developed. ATOPS is an automation system for operation of a nuclear power plant (NPP) which can monitor signals, diagnose statuses, and generate control actions according to corresponding operating procedures, without any human operator's help. Main functions of ATOPS are anomaly detection function and procedure execution function, but only the procedure execution function is implemented because this work is just the first step. In the procedure execution function, operating procedures of NPP are analyzed and modeled using Fuzzy Colored Petri Nets (FCPN), and executed depending on decision making of the inference engine. In this work, an ATOPS prototype is developed in order to demonstrate its feasibility and it is also validated using FISA-2/WS simulator. The validation is performed for the cases of a loss of coolant accident (LOCA) and a steam generator tube rupture (SGTR). The simulation results show that ATOPS works correctly in the emergency situations
Approach to plant automation with evolving technology

International Nuclear Information System (INIS)

White, J.D.

1989-01-01

The US Department of Energy has provided support to Oak Ridge National Laboratory in order to pursue research leading to advanced, automated control of new innovative liquid-metal-cooled nuclear power plants. The purpose of this effort is to conduct research that will help to ensure improved operability, reliability, and safety for advanced LMRs. The plan adopted to achieve these program goals in an efficient and timely manner consists of utilizing, and advancing where required, state-of-the-art controls technology through close interaction with other national laboratories, universities, industry and utilities. A broad range of applications for the control systems strategies and the design environment developed in the course of this program is likely. A natural evolution of automated control in nuclear power plants is envisioned by ORNL to be a phased transition from today's situation of some analog control at the subsystem level with significant operator interaction to the future capability for completely automated digital control with operator supervision. The technical accomplishments provided by this program will assist the industry to accelerate this transition and provide greater economy and safety. The development of this transition to advanced, automated control system designs is expected to have extensive benefits in reduced operating costs, fewer outages, enhanced safety, improved licensability, and improved public acceptance for commercial nuclear power plants. 24 refs
Approach to plant automation with evolving technology

International Nuclear Information System (INIS)

White, J.D.

1989-01-01

This paper reports that the U.S. Department of Energy has provided support to Oak Ridge National Laboratory in order to pursue research leading to advanced, automated control of new innovative liquid-metal-cooled nuclear power plants. The purpose of this effort is to conduct research that will help to ensure improved operability, reliability, and safety for advanced LMRs. The plan adopted to achieve these program goals in an efficient and timely manner consists of utilizing, and advancing where required, state-of-the art controls technology through close interaction with other national laboratories, universities, industry and utilities. A broad range of applications for the control systems strategies and the design environment developed in the course of this program is likely. A natural evolution of automated control in nuclear power plants is envisioned by ORNL to be a phased transition from today's situation of some analog control at the subsystem level with significant operator interaction to the future capability for completely automated digital control with operator supervision. The technical accomplishments provided by this program will assist the industry to accelerate this transition and provide greater economy and safety. The development of this transition to advanced, automated control system designs is expected to have extensive benefits in reduced operating costs, fewer outages, enhanced safety, improved licensability, and improved public acceptance for commercial nuclear power plants
Safeguards and security considerations for automated and robotic systems

Energy Technology Data Exchange (ETDEWEB)

Jordan, S.E.; Jaeger, C.D.

1994-09-01

Within the reconfigured Nuclear Weapons Complex there will be a large number of automated and robotic (A&R) systems because of the many benefits derived from their use. To meet the overall security requirements of a facility, consideration must be given to those systems that handle and process nuclear material. Since automation and robotics is a relatively new technology, not widely applied to the Nuclear Weapons Complex, safeguards and security (S&S) issues related to these systems have not been extensively explored, and no guidance presently exists. The goal of this effort is to help integrate S&S into the design of future A&R systems. Towards this, the authors first examined existing A and R systems from a security perspective to identify areas of concern and possible solutions of these problems. They then were able to develop generalized S&S guidance and design considerations for automation and robotics.
Using New Technologies for Design, Modernization and Automation of Systems and Processes Related with Nuclear Applications. Technical Report of an Experts' Meeting

International Nuclear Information System (INIS)

2016-04-01

In recent years the International Atomic Energy Agency has organized a series of technical cooperation projects aimed at expanding and strengthening the capacities of laboratories that work with nuclear instrumentation, as well as developing prototypes of instruments and interfaces which can respond to different needs in nuclear applications in the Latin America Caribbean (RLA) region. The introduction of advanced technologies for the design of instrumentation, interfaces and devices specialized and for work automation systems or processes related nuclear applications, has enabled to make better use of the available instrumentation. Repair work and modernization are an alternative to counter the lack of maintenance services by equipment suppliers that exceed the time life provided by manufacturers (planned obsolescence). Not only do specialized designs allow to solve specific needs, but often help reduce costs and the deadlines of work. An expert' meeting was held under the regional project RLA1011 (Support Automation Systems and Processes in Nuclear Facilities) to prepare a technical report that would provide recommendations to Member States of the IAEA on the current state of development several advanced technologies and their main fields of application, including examples of work in the region within the framework of this project. Eleven analytics entirely in Spanish from participating Member States are included in this publication
A Project in Support of Nuclear Technology Cooperation

International Nuclear Information System (INIS)

Lee, Kyu Jung; Choi, Pyong Hoon; Yi, Ji Ho and others

2004-12-01

The result and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-Rom DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Effective management of computer codes for nuclear application and establishment of information exchange mechanism for rapid technical support. - acquisition of nuclear computer codes from NEA Data Bank an registration of new software developed by domestic organization
Laboratory automation in clinical bacteriology: what system to choose?

Science.gov (United States)

Croxatto, A; Prod'hom, G; Faverjon, F; Rochais, Y; Greub, G

2016-03-01

Automation was introduced many years ago in several diagnostic disciplines such as chemistry, haematology and molecular biology. The first laboratory automation system for clinical bacteriology was released in 2006, and it rapidly proved its value by increasing productivity, allowing a continuous increase in sample volumes despite limited budgets and personnel shortages. Today, two major manufacturers, BD Kiestra and Copan, are commercializing partial or complete laboratory automation systems for bacteriology. The laboratory automation systems are rapidly evolving to provide improved hardware and software solutions to optimize laboratory efficiency. However, the complex parameters of the laboratory and automation systems must be considered to determine the best system for each given laboratory. We address several topics on laboratory automation that may help clinical bacteriologists to understand the particularities and operative modalities of the different systems. We present (a) a comparison of the engineering and technical features of the various elements composing the two different automated systems currently available, (b) the system workflows of partial and complete laboratory automation, which define the basis for laboratory reorganization required to optimize system efficiency, (c) the concept of digital imaging and telebacteriology, (d) the connectivity of laboratory automation to the laboratory information system, (e) the general advantages and disadvantages as well as the expected impacts provided by laboratory automation and (f) the laboratory data required to conduct a workflow assessment to determine the best configuration of an automated system for the laboratory activities and specificities. Copyright © 2016 The Authors. Published by Elsevier Ltd.. All rights reserved.
Longitudinal analysis of the temporal evolution of Acinetobacter baumannii strains in Ohio, USA, by using rapid automated typing methods.

Directory of Open Access Journals (Sweden)

Brooke K Decker

Full Text Available Genotyping methods are essential to understand the transmission dynamics of Acinetobacter baumannii. We examined the representative genotypes of A. baumannii at different time periods in select locations in Ohio, using two rapid automated typing methods: PCR coupled with electrospray ionization mass spectrometry (PCR/ESI-MS, a form of multi-locus sequence typing (MLST, and repetitive-sequence-based-PCR (rep-PCR. Our analysis included 122 isolates from 4 referral hospital systems, in 2 urban areas of Ohio. These isolates were associated with outbreaks at 3 different time periods (1996, 2000 and 2005-2007. Type assignments of PCR/ESI-MS and rep-PCR were compared to each other and to worldwide (WW clone types. The discriminatory power of each method was determined using the Simpson's index of diversity (DI. We observed that PCR/ESI-MS sequence type (ST 14, corresponding to WW clone 3, predominated in 1996, whereas ST 12 and 14 co-existed in the intermediate period (2000 and ST 10 and 12, belonging to WW clone 2, predominated more recently in 2007. The shift from WW clone 3 to WW clone 2 was accompanied by an increase in carbapenem resistance. The DI was approximately 0.74 for PCR/ESI-MS, 0.88 for rep-PCR and 0.90 for the combination of both typing methods. We conclude that combining rapid automated typing methods such as PCR/ESI-MS and rep-PCR serves to optimally characterize the regional molecular epidemiology of A. baumannii. Our data also sheds light on the changing sequence types in an 11 year period in Northeast Ohio.
Proceedings of the 1988 IEEE international conference on robotics and automation. Volume 1

International Nuclear Information System (INIS)

Anon.

1988-01-01

These proceedings compile the papers presented at the international conference (1988) sponsored by IEEE Council on ''Robotics and Automation''. The subjects discussed were: automation and robots of nuclear power stations; algorithms of multiprocessors; parallel processing and computer architecture; and U.S. DOE research programs on nuclear power plants
Human resources in the Japanese nuclear industry

International Nuclear Information System (INIS)

Katayama, M.

1995-01-01

Japan is becoming rapidly a nation with an elderly population. Japanese students are turning away from the manufacturing industries, including the nuclear industry, and turning towards more service oriented industries that are considered to be cleaner and to pay better. Studies have been performed to devise ways to attract young workers to the nuclear industry, which is projected to continue to grown under the current long range energy plants. The paper summarizes the findings and recommendations of the recent studies conducted by the nuclear industry and academic circles. All studies point out that insufficient emphasis is placed on science in the present Japanese educational programme and that implementation of effective programmes to revitalize education in science is most urgently needed to keep Japan in the forefront of high technology. Utilization of advanced computer technology and automation is promoted to improve working conditions and efficiency in the nuclear industry. In addition, the establishment of a professional status of engineers and technicians will be vital for an effective utilization of qualified workers in the nuclear industry. (author). 3 refs, 1 tab
A simple rapid process for semi-automated brain extraction from magnetic resonance images of the whole mouse head.

Science.gov (United States)

Delora, Adam; Gonzales, Aaron; Medina, Christopher S; Mitchell, Adam; Mohed, Abdul Faheem; Jacobs, Russell E; Bearer, Elaine L

2016-01-15

Magnetic resonance imaging (MRI) is a well-developed technique in neuroscience. Limitations in applying MRI to rodent models of neuropsychiatric disorders include the large number of animals required to achieve statistical significance, and the paucity of automation tools for the critical early step in processing, brain extraction, which prepares brain images for alignment and voxel-wise statistics. This novel timesaving automation of template-based brain extraction ("skull-stripping") is capable of quickly and reliably extracting the brain from large numbers of whole head images in a single step. The method is simple to install and requires minimal user interaction. This method is equally applicable to different types of MR images. Results were evaluated with Dice and Jacquard similarity indices and compared in 3D surface projections with other stripping approaches. Statistical comparisons demonstrate that individual variation of brain volumes are preserved. A downloadable software package not otherwise available for extraction of brains from whole head images is included here. This software tool increases speed, can be used with an atlas or a template from within the dataset, and produces masks that need little further refinement. Our new automation can be applied to any MR dataset, since the starting point is a template mask generated specifically for that dataset. The method reliably and rapidly extracts brain images from whole head images, rendering them useable for subsequent analytical processing. This software tool will accelerate the exploitation of mouse models for the investigation of human brain disorders by MRI. Copyright © 2015 Elsevier B.V. All rights reserved.
Automated Test Case Generation for an Autopilot Requirement Prototype

Science.gov (United States)

Giannakopoulou, Dimitra; Rungta, Neha; Feary, Michael

2011-01-01

Designing safety-critical automation with robust human interaction is a difficult task that is susceptible to a number of known Human-Automation Interaction (HAI) vulnerabilities. It is therefore essential to develop automated tools that provide support both in the design and rapid evaluation of such automation. The Automation Design and Evaluation Prototyping Toolset (ADEPT) enables the rapid development of an executable specification for automation behavior and user interaction. ADEPT supports a number of analysis capabilities, thus enabling the detection of HAI vulnerabilities early in the design process, when modifications are less costly. In this paper, we advocate the introduction of a new capability to model-based prototyping tools such as ADEPT. The new capability is based on symbolic execution that allows us to automatically generate quality test suites based on the system design. Symbolic execution is used to generate both user input and test oracles user input drives the testing of the system implementation, and test oracles ensure that the system behaves as designed. We present early results in the context of a component in the Autopilot system modeled in ADEPT, and discuss the challenges of test case generation in the HAI domain.

Background and perspective on rapid progress and deepening of international development of nuclear industry-composition of international nuclear energy business 'cooperation and competition'

International Nuclear Information System (INIS)

Kano, Tokio; Kanda, Keji; Ishizuka, Nobuo

2005-01-01

Based on the recognition that international development of nuclear industry was important by a viewpoint of international cooperation to neighboring Asian area and also it was the trump that defeated a feeling of domestic confinement, the Japan Atomic Industrial Forum (JAIF) founded Nuclear energy international development gathering' in November 2004. On that occasion our magazine (March, 2005 issue) featured 'prospects and problem of the international development of nuclear energy use'. Slightly for half a year afterwards this nuclear energy international development has been rapidly deepened and become a close-up as a policy of an important strategy of the field of nuclear energy that the government and the private sector were united to make. Therefore the nuclear energy international development was secondly featured from multidirectional points of view such as a background of nuclear energy international development, composition of international nuclear energy business, a main strategy of three makers, approach of finance / a business firm. (T. Tanaka)
Safeguards and security considerations for automated and robotic systems

International Nuclear Information System (INIS)

Jordan, S.E.; Jaeger, C.D.

1994-01-01

Within the reconfigured Nuclear Weapons Complex there will be a large number of automated and robotic (A ampersand R) systems because of the many benefits derived from their use. To meet the overall security requirements of a facility, consideration must be given to those systems that handle and process nuclear material. Since automation and robotics is a relatively new technology, not widely applied to the Nuclear Weapons Complex, safeguards and security (S ampersand S) issues related to these systems have not been extensively explored, and no guidance presently exists. The goal of this effort is to help integrate S ampersand S into the design of future A ampersand R systems. Towards this, the authors first examined existing A and R systems from a security perspective to identify areas of concern and possible solutions of these problems. They then were able to develop generalized S ampersand S guidance and design considerations for automation and robotics
Safeguards and security considerations for automated and robotic systems

International Nuclear Information System (INIS)

Jordan, S.E.; Jaeger, C.D.

1994-01-01

Within the reconfigured Nuclear Weapons Complex there will be a large number of automated and robotic (A ampersand R) systems because of the many benefits derived from their use. To meet the overall security requirements of a facility, consideration must be given to those systems that handle and process nuclear material. Since automation and robotics is a relatively new technology, not widely applied to the Nuclear Weapons Complex, safeguards and security (S ampersand S) issues related to these systems have not been extensively explored, and no guidance presently exists. The goal of this effort is to help integrate S ampersand S into the design of future A ampersand R systems. Towards this, we first examined existing A ampersand R systems from a security perspective to identify areas of concern and possible solutions to these problems. We then were able to develop generalized S ampersand S guidance and design considerations for automation and robotics
Determination of oxygen potentials and O/M ratios of oxide nuclear reactor fuels by means of an automated solid state galvanic cell

International Nuclear Information System (INIS)

Toci, F.; Cambini, M.

1987-01-01

An automated version of the electromotive force (emf) cell for the determination of oxygen activities and oxygen to metal ratios of oxide nuclear reactor fuel, irradiated or not, is reported together with some measurements. 9 figs., 17 refs. In appendix a method is described for preparing suitable electrolyte crucibles
Automation and mechanization of in-service inspection of selected equipment in FRG's nuclear power plants

International Nuclear Information System (INIS)

Metke, E.

1988-01-01

The procedures and equipment are described for the automation and mechanization of in-service inspection in nuclear power plants in the FRG, used by the KWU company. Checks of the pressure vessel are done by visual means using a colour tv camera, the method of eddy currents and the ultrasonic method. An analysis is made of the time schedule of ultrasonic inspections, and the central column manipulator is described which allows to check all internal regions of the pressure vessel. Attention is also devoted to other devices, e.g., those for prestressing shanks, cleaning shanks, cleaning thread apertures, etc. A combined probe using the ultrasonic method and the eddy current method serves the inspection of heat exchange tubes in the steam generator. For inspecting the primary circuit the KWU company uses devices for checking and working the inner surface of pipes. Briefly described are examples of using KWU equipment in nuclear power plants in CMEA countries. (Z.M.). 11 figs., 6 refs
Development of automated equipment for reduction of personnel radiation exposure in nuclear power plants

International Nuclear Information System (INIS)

Ogushi, Akira; Fujii, Masaaki; Mizuno, Katsuhiro.

1976-01-01

Described are a mobile remote inspection system and an automatic analyzer for radioactive nuclides in reactor coolant now being developed as a means of reducing personnel radiation exposure in nuclear power plants. In the mobile remote inspection system ''TELEPAT'', a self-propelled vehicle equipped with a thermometer, accelerometer, microphone, ionization chamber, etc. is remote operated from the main control room to inspect the equipment in the reactor building. The automatic analyzer for radioactive nuclides in reactor coolant automates the series of operations ranging from sampling of reactor coolant to measurement of radioactivity and analyses of measured data, with a view to saving labor in radioactivity analysis work while reducing exposure of personnel to radiation. (auth.)
A rapid radiobioassay method for strontium estimation in nuclear/radiological emergencies

International Nuclear Information System (INIS)

Wankhede, Sonal; Sawant, Pramilla D.; Rao, D.D.; Pradeepkumar, K.S.

2014-01-01

During a nuclear/radiological emergency, workers as well as members of the public (MOP) may get internally contaminated with the radionuclides like Sr and Cs. In such situations, a truly rapid radiobioassay method is required to screen a large number of people in order to assess internal contamination and also to decide on subsequent medical intervention. The current precipitation method used at Bioassay Lab., Trombay is quite lengthy and laborious. Efforts are being made to optimize bioassay methods at Bhabha Atomic Research Centre using Solid Extraction Chromatography (SEC) technique for emergency response. The present work reports standardization of SEC technique for rapid estimation of Sr in urine samples. The method standardized using Sr spec is simpler, shorter, result in higher recoveries and reproducible results. It is most suitable for quick dose assessment of 90 Sr in bioassay samples in case of emergency
Remote fabrication of nuclear fuel: a secure automated fabrication overview

International Nuclear Information System (INIS)

Nyman, D.H.; Benson, E.M.; Yatabe, J.M.; Nagamoto, T.T.

1981-01-01

An automated line for the fabrication of breeder reactor fuel pins is being developed. The line will be installed in the Fuels and Materials Examination Facility (FMEF) presently under construction at the Hanford site near Richland, Washington. The application of automation and remote operations to fuel processing technology is needed to meet program requirements of reduced personnel exposure, enhanced safeguards, improved product quality, and increased productivity. Commercially available robots are being integrated into operations such as handling of radioactive material within a process operation. These and other automated equipment and chemistry analyses systems under development are described
Automation-aided Task Loads Index based on the Automation Rate Reflecting the Effects on Human Operators in NPPs

International Nuclear Information System (INIS)

Lee, Seungmin; Seong, Poonghyun; Kim, Jonghyun

2013-01-01

Many researchers have found that a high automation rate does not guarantee high performance. Therefore, to reflect the effects of automation on human performance, a new estimation method of the automation rate that considers the effects of automation on human operators in nuclear power plants (NPPs) was suggested. These suggested measures express how much automation support human operators but it cannot express the change of human operators' workload, whether the human operators' workload is increased or decreased. Before considering automation rates, whether the adopted automation is good or bad might be estimated in advance. In this study, to estimate the appropriateness of automation according to the change of the human operators' task loads, automation-aided task loads index is suggested based on the concept of the suggested automation rate. To insure plant safety and efficiency on behalf of human operators, various automation systems have been installed in NPPs, and many works which were previously conducted by human operators can now be supported by computer-based operator aids. According to the characteristics of the automation types, the estimation method of the system automation and the cognitive automation rate were suggested. The proposed estimation method concentrates on the effects of introducing automation, so it directly express how much the automated system support human operators. Based on the suggested automation rates, the way to estimate how much the automated system can affect the human operators' cognitive task load is suggested in this study. When there is no automation, the calculated index is 1, and it means there is no change of human operators' task load
An automation of physics research on base of open standards

International Nuclear Information System (INIS)

Smirnov, V.A.

1997-01-01

A wide range of problems is considered concerning an automation of Laboratory of High Energies, JINR set-ups oriented to carry out the experimental researches in high energy and relativistic nuclear physics. Electronics of discussed automation systems is performed in open standards. Main peculiarities in the creation process of automation tools for experimental set-ups, stands and accelerators are shown. Some possibilities to build some accelerator control subsystems on base of industrial automation methods and techniques are discussed
Automatic sample changer control software for automation of neutron activation analysis process in Malaysian Nuclear Agency

Science.gov (United States)

Yussup, N.; Ibrahim, M. M.; Rahman, N. A. A.; Mokhtar, M.; Salim, N. A. A.; Soh@Shaari, S. C.; Azman, A.; Lombigit, L.; Azman, A.; Omar, S. A.

2018-01-01

Most of the procedures in neutron activation analysis (NAA) process that has been established in Malaysian Nuclear Agency (Nuclear Malaysia) since 1980s were performed manually. These manual procedures carried out by the NAA laboratory personnel are time consuming and inefficient especially for sample counting and measurement process. The sample needs to be changed and the measurement software needs to be setup for every one hour counting time. Both of these procedures are performed manually for every sample. Hence, an automatic sample changer system (ASC) that consists of hardware and software is developed to automate sample counting process for up to 30 samples consecutively. This paper describes the ASC control software for NAA process which is designed and developed to control the ASC hardware and call GammaVision software for sample measurement. The software is developed by using National Instrument LabVIEW development package.
Dilepton distributions at backward rapidities

International Nuclear Information System (INIS)

Betemps, M. A.; Ducati, M. B. Gay; Oliveira, E. G. de

2006-01-01

The dilepton production at backward rapidities in pAu and pp collisions at RHIC and LHC energies is investigated in the dipole approach. The results are shown through the nuclear modification ratio R pA considering transverse momentum and rapidity spectra. The dilepton modification ratio presents interesting behavior at the backward rapidities when compared with the already known forward ones, since it is related with the large x kinematical region that is being probed. The rapidity dependence of the nuclear modification ratio in the dilepton production is strongly dependent on the Bjorken x behavior of the nuclear structure function ratio R F 2 =F 2 A /F 2 p . The R pA transverse momentum dependence at backward rapidities is modified due to the large x nuclear effects: at RHIC energies, for instance, the ratio R pA is reduced as p T increases, presenting an opposite behavior when compared with the forward one. It implies that the dilepton production at backward rapidities should carry information of the nuclear effects at large Bjorken x, as well as that it is useful to investigate the p T dependence of the observables in this kinematical regime
Automated Installation Verification of COMSOL via LiveLink for MATLAB

International Nuclear Information System (INIS)

Crowell, Michael W

2015-01-01

Verifying that a local software installation performs as the developer intends is a potentially time-consuming but necessary step for nuclear safety-related codes. Automating this process not only saves time, but can increase reliability and scope of verification compared to ''hand'' comparisons. While COMSOL does not include automatic installation verification as many commercial codes do, it does provide tools such as LiveLink"T"M for MATLAB® and the COMSOL API for use with Java® through which the user can automate the process. Here we present a successful automated verification example of a local COMSOL 5.0 installation for nuclear safety-related calculations at the Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR).
Automated Installation Verification of COMSOL via LiveLink for MATLAB

Energy Technology Data Exchange (ETDEWEB)

Crowell, Michael W [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-01-01

Verifying that a local software installation performs as the developer intends is a potentially time-consuming but necessary step for nuclear safety-related codes. Automating this process not only saves time, but can increase reliability and scope of verification compared to ‘hand’ comparisons. While COMSOL does not include automatic installation verification as many commercial codes do, it does provide tools such as LiveLink™ for MATLAB® and the COMSOL API for use with Java® through which the user can automate the process. Here we present a successful automated verification example of a local COMSOL 5.0 installation for nuclear safety-related calculations at the Oak Ridge National Laboratory’s High Flux Isotope Reactor (HFIR).
Control and automation systems

International Nuclear Information System (INIS)

Schmidt, R.; Zillich, H.

1986-01-01

A survey is given of the development of control and automation systems for energy uses. General remarks about control and automation schemes are followed by a description of modern process control systems along with process control processes as such. After discussing the particular process control requirements of nuclear power plants the paper deals with the reliability and availability of process control systems and refers to computerized simulation processes. The subsequent paragraphs are dedicated to descriptions of the operating floor, ergonomic conditions, existing systems, flue gas desulfurization systems, the electromagnetic influences on digital circuits as well as of light wave uses. (HAG) [de
Automated injection of a radioactive sample for preparative HPLC with feedback control

International Nuclear Information System (INIS)

Iwata, Ren; Yamazaki, Shigeki

1990-01-01

The injection of a radioactive reaction mixture into a preparative HPLC column has been automated with computer control for rapid purification of routinely prepared positron emitting radiopharmaceuticals. Using pneumatic valves, a motor-driven pump and a liquid level sensor, two intelligent injection methods for the automation were compared with regard to efficient and rapid sample loading into a 2 mL loop of the 6-way valve. One, a precise but rather slow method, was demonstrated to be suitable for purification of 18 F-radiopharmaceuticals, while the other, due to its rapid operation, was more suitable for 11 C-radiopharmaceuticals. A sample volume of approx 0.5 mL can be injected onto a preparative HPLC column with over 90% efficiency with the present automated system. (author)
Advanced I and C systems for nuclear power plants feedback of experience

International Nuclear Information System (INIS)

Prehler Heinz Josef

2001-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. TELEPERM XP is primarily oriented to automation of the non safety related part of the power plant process. Such applications involve extensive open and closed loop control systems and encompass all tasks required for process control via the man-machine interface. Therefore the TELEPERM XP system consists of the AS 620 automation system, the OM 690 process control and management system, the ES 680 engineering system, the DS 670 diagnostic system and the SIMATIC NET bus system. Three versions of automation systems are available: for standard automation, for fail safe automation of safety related tasks and for turbine automation. TELEPERM XS is designed to meet all the requirements on I and C important to safety in nuclear power plants. Typical applications include reactor protection (RPS) and Engineered Safety Features Actuation System functions (ESFAS). TELEPERM XS has been rapidly accepted by the market and has accumulated an extensive operational experience. The expected advantages, namely, reduced space requirements, consistent documentation, improved ergonomics, reduced testing effort, less repair have been confirmed by the operation. The new possibilities to apply intelligent diagnostic methods have been only applied in few cases. Very good service records from a broad field of safety application prove that it is right to use digital I and C systems for safety tasks. The expected advantages such as reduced space requirements, less repairs and less effort for periodic tests, have been confirmed by practical experience. For the future, use of digital I and C systems for safety
Synthesis of Automated Vehicle Legislation

Science.gov (United States)

2017-10-01

This report provides a synthesis of issues addressed by state legislation regarding automated vehicles (AV); AV technologies are rapidly evolving and many states have developed legislation to govern AV testing and deployment and to assure safety on p...
Development of an automated remote inspection system for the interior of the primary containment vessel of a nuclear power plant

International Nuclear Information System (INIS)

Senoo, Makoto; Yoshida, Tomiharu; Omote, Tatsuyuki; Tanaka, Keiji; Koga, Kazunori

1996-01-01

An automated remote inspection system has been developed for the interior of the primary containment vessel of a nuclear power plant. This system consists of an inspection robot and an operator's console. The inspection robot travels along a monorail provided in the interior of the primary containment vessel. The operator's console is located in the central control room of the power plant. We have made efforts to downsize the robot and automate the inspection and monitoring machinery. As for downsizing the robot, a 152 mm wide, 290 mm high cross-sectional area and 15 kg weight can be realized using commercially available small sensors and rearranging the parts in those sensors. As for automating the inspection and monitoring, several monitoring functions are developed using image processing, frequency analysis and other techniques applied to signals from sensors such as an ITV camera, an infrared camera and a microphone, which are mounted on the robot. Endurance tests show resistance of the robot to radiational and thermal conditions is adequate for actual use in actual power plants. (author)
Completely automated measurement facility (PAVICOM) for track-detector data processing

CERN Document Server

Aleksandrov, A B; Feinberg, E L; Goncharova, L A; Konovalova, N S; Martynov, A G; Polukhina, N G; Roussetski, A S; Starkov, NI; Tsarev, V A

2004-01-01

A review of technical capabilities and investigations performed using the completely automated measuring facility (PAVICOM) is presented. This very efficient facility for track-detector data processing in the field of nuclear and high-energy particle physics has been constructed in the Lebedev physical institute. PAVICOM is widely used in Russia for treatment of experimental data from track detectors (emulsion and solid-state trackers) in high- and low-energy physics, cosmic ray physics, etc. PAVICOM provides an essential improvement of the efficiency of experimental studies. In contrast to semi-automated microscopes widely used until now, PAVICOM is capable of performing completely automated measurements of charged particle tracks in nuclear emulsions and track detectors without employing hard visual work. In this case, track images are recorded by CCD cameras and then are digitized and converted into files. Thus, experimental data processing is accelerated by approximately a thousand times. Completely autom...

Automation-aided Task Loads Index based on the Automation Rate Reflecting the Effects on Human Operators in NPPs

Energy Technology Data Exchange (ETDEWEB)

Lee, Seungmin; Seong, Poonghyun [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2013-05-15

Many researchers have found that a high automation rate does not guarantee high performance. Therefore, to reflect the effects of automation on human performance, a new estimation method of the automation rate that considers the effects of automation on human operators in nuclear power plants (NPPs) was suggested. These suggested measures express how much automation support human operators but it cannot express the change of human operators' workload, whether the human operators' workload is increased or decreased. Before considering automation rates, whether the adopted automation is good or bad might be estimated in advance. In this study, to estimate the appropriateness of automation according to the change of the human operators' task loads, automation-aided task loads index is suggested based on the concept of the suggested automation rate. To insure plant safety and efficiency on behalf of human operators, various automation systems have been installed in NPPs, and many works which were previously conducted by human operators can now be supported by computer-based operator aids. According to the characteristics of the automation types, the estimation method of the system automation and the cognitive automation rate were suggested. The proposed estimation method concentrates on the effects of introducing automation, so it directly express how much the automated system support human operators. Based on the suggested automation rates, the way to estimate how much the automated system can affect the human operators' cognitive task load is suggested in this study. When there is no automation, the calculated index is 1, and it means there is no change of human operators' task load.
Automated system of control of radioactive liquid effluents of patients submitted to therapy in hospitals of nuclear medicine (SACEL); Sistema automatizado de control de efluentes liquidos radiactivos de pacientes sometidos a terapia en hospitales de medicina nuclear (SACEL)

Energy Technology Data Exchange (ETDEWEB)

Ruiz C, M A; Rivero G, T; Celis del Angel, L; Sainz M, E; Molina, G [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2006-07-01

Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote
DESIGN OF SMALL AUTOMATION WORK CELL SYSTEM DEMONSTRATIONS

International Nuclear Information System (INIS)

TURNER, C.; PEHL, J.

2000-01-01

The introduction of automation systems into many of the facilities dealing with the production, use and disposition of nuclear materials has been an ongoing objective. Many previous attempts have been made, using a variety of monolithic and, in some cases, modular technologies. Many of these attempts were less than successful, owing to the difficulty of the problem, the lack of maturity of the technology, and over optimism about the capabilities of a particular system. Consequently, it is not surprising that suggestions that automation can reduce worker Occupational Radiation Exposure (ORE) levels are often met with skepticism and caution. The development of effective demonstrations of these technologies is of vital importance if automation is to become an acceptable option for nuclear material processing environments. The University of Texas Robotics Research Group (UTRRG) has been pursuing the development of technologies to support modular small automation systems (each of less than 5 degrees-of-freedom) and the design of those systems for more than two decades. Properly designed and implemented, these technologies have a potential to reduce the worker ORE associated with work in nuclear materials processing facilities. Successful development of systems for these applications requires the development of technologies that meet the requirements of the applications. These application requirements form a general set of rules that applicable technologies and approaches need to adhere to, but in and of themselves are generally insufficient for the design of a specific automation system. For the design of an appropriate system, the associated task specifications and relationships need to be defined. These task specifications also provide a means by which appropriate technology demonstrations can be defined. Based on the requirements and specifications of the operations of the Advanced Recovery and Integrated Extraction System (ARIES) pilot line at Los Alamos National
Pyrochemical processing automation at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Dennison, D.K.; Domning, E.E.; Seivers, R.

1991-01-01

Lawrence Livermore National Laboratory (LLNL) is developing a fully automated system for pyrochemical processing of special nuclear materials (SNM). The system utilizes a glove box, an automated tilt-pour furnace (TPF), an IBM developed gantry robot, and specialized automation tooling. All material handling within the glove box (i.e., furnace loading, furnace unloading, product and slag separation, and product packaging) is performed automatically. The objectives of the effort are to increase process productivity, decrease operator radiation, reduce process wastes, and demonstrate system reliability and availability. This paper provides an overview of the automated system hardware, outlines the overall operations sequence, and discusses the current status
Computer automation and artificial intelligence

International Nuclear Information System (INIS)

Hasnain, S.B.

1992-01-01

Rapid advances in computing, resulting from micro chip revolution has increased its application manifold particularly for computer automation. Yet the level of automation available, has limited its application to more complex and dynamic systems which require an intelligent computer control. In this paper a review of Artificial intelligence techniques used to augment automation is presented. The current sequential processing approach usually adopted in artificial intelligence has succeeded in emulating the symbolic processing part of intelligence, but the processing power required to get more elusive aspects of intelligence leads towards parallel processing. An overview of parallel processing with emphasis on transputer is also provided. A Fuzzy knowledge based controller for amination drug delivery in muscle relaxant anesthesia on transputer is described. 4 figs. (author)
Nuclear applications in life sciences

International Nuclear Information System (INIS)

Uenak, P.

2009-01-01

Radioactivity has revolutionized life sciences during the last century, and it is still an indispensable tool. Nuclear Medicine, Radiation Biology and Radiotherapy, Dosimetry and Medical Radiation Physics, Nutrition and Environmental Problems Relevant Health are significant application fields of Nuclear Sciences. Nuclear medicine today is a well established branch of medicine. Radionuclides and radiopharmaceuticals play a key role both in diagnostic investigations and therapy-Both cyclotron and reactor produced radionuclides find application, the former more in diagnostic studies and the latter in therapy. New therapy applications such as bor neutron therapy are increasing by time together with the technological improvements in imaging systems such as PET and SPECT. Radionuclides and radiopharmaceuticals play important role in both therapy and imaging. However cyclotron produced radionuclides have been using generally in imaging purposes while reactor produced radionuclides have also therapeutic applications. With the advent of emission tomography, new vistas for probing biochemistry in vivo have been opened. The radio chemist faces an ever-increasing challenge of designing new tracers for diagnostic and therapeutic applications. Rapid, efficient and automated methods of radionuclide and precursor production, labeling of biomolecules, and quality control need to be developed. The purpose of this article is a short interface from Nuclear Medicine, Radiation Biology and Radiotherapy, Dosimetry and Medical Radiation Physics Applications of Nuclear Sciences.
A facile and rapid automated synthesis of 3'-deoxy-3'-[18F]fluorothymidine

International Nuclear Information System (INIS)

Tang Ganghua; Tang Xiaolan; Wen Fuhua; Wang Mingfang; Li Baoyuan

2010-01-01

Aim: To develop a simplified and fully automated synthesis procedure of 3'-deoxy-3'-[ 18 F]fluorothymidine ([ 18 F]FLT) using PET-MF-2V-IT-I synthesis module. Methods: Synthesis of [ 18 F]FLT was performed using PET-MF-2V-IT-I synthesis module by one-pot two-step reaction procedure, including nucleophilic fluorination of 3-N-t-butoxycarbonyl-1-[5'-O-(4,4'-dimethoxy triphenylmethyl)-2'-deoxy-3'-O-(4-nitrobenzenesulfonyl) -β-D-threopentofuranosyl]thymine (15 mg) as the precursor molecule with [ 18 F]fluoride, and subsequent hydrolysis of the protecting group with 1.0 M HCl at the same reaction vessel and purification with SEP PAK cartridges instead of the HPLC system. Results: The automated synthesis of [ 18 F]FLT with SEP PAK purification gave corrected radiochemical yield of 23.2±2.6% (n=6, uncorrected yield: 16-22%) and radiochemical purity of >97% within the total synthesis time of 35 min. Conclusion: The fully one-pot automated synthesis procedure with SEP PAK purification can be applied to the fully automated synthesis of [ 18 F]FLT using commercial [ 18 F]FDG synthesis module.
Process computers automate CERN power supply installations

International Nuclear Information System (INIS)

Ullrich, H.; Martin, A.

1974-01-01

Higher standards of performance and reliability in the power plants of large particle accelerators necessitate increasing use of automation. The CERN (European Nuclear Research Centre) in Geneva started to employ process computers for plant automation at an early stage in its history. The great complexity and extent of the plants for high-energy physics first led to the setting-up of decentralized automatic systems which are now being increasingly combined into one interconnected automation system. One of these automatic systems controls and monitors the extensive power supply installations for the main ring magnets in the experimental zones. (orig.) [de
Computerized control and management at the Temelin nuclear power plant

International Nuclear Information System (INIS)

Mitosinka, J.; Korec, J.

1992-01-01

The proposed automation of the nuclear power plant control system includes a division of the control system into three hierarchic levels, supplemented with an additional level. These comprise the automated system of control of technological processes, the all-plant control of the power-generating process, the control of backup activities and of technical and economic activities, and top managerial control. The efficiency of the nuclear power plant operation, i.e. attainment of the maximum electricity output with minimum costs while securing the required safety, is the principal criterion in the design of the data model. Listed are tasks that would lend themselves to automation within the automated system of nuclear power plant control, and the basic scheme of their automation as follows from an analysis performed at the Temelin nuclear power plant. (Z.S). 2 figs., 2 refs
Flexible manufacturing systems and their relevance in nuclear fuel fabrication in India

International Nuclear Information System (INIS)

Ramakumar, M.S.

1989-01-01

Fabrication of nuclear reactor fuel bundle involves several materials and a number of complicated technologies and the process of manufacture has to conform to stringent standards. The Indian Nuclear Programme relies heavily on indigeneous capability of manufacture of nuclear fuels as well as automation of the related facilities. Automation of the existing nuclear facilities is a challenge in view of the characteristic plant environments and process demands as well as the various mechanical and metallurgical steps involved. This paper discusses their requirements and the measures initiated for achieving a high order of automation in Indian nuclear facilities. As a first step, specific automation steps are being incorporated in the existing plants. Such interface automation will enhance productivity and avoid the need for building new totally automated palnts. Flexible manufacturing system as applied here, has a different connotation vis-a-vis conventional manufacturing industry. Robotic devices, even for stacking jobs, have not been used on a large scale the world over. (author). 6 figs
Automated 741 document preparation: Oak Ridge National Laboratory's Automated Safeguards Information System (OASIS)

International Nuclear Information System (INIS)

Austin, H.C.; Gray, L.M.

1982-01-01

OASIS has been providing for Oak Ridge National Laboratory's total safeguards needs since being place on line in April 1980. The system supports near real-time nuclear materials safeguards and accountability control. The original design of OASIS called for an automated facsimile of a 741 document to be prepared as a functional by-product of updating the inventory. An attempt was made to utilize, intact, DOE-Albuquerque's automated 741 system to generate the facsimile; however, the five page document produced proved too cumbersome. Albuquerque's programs were modified to print an original 741 document utilizing standard DOE/NRC 741 forms. It is felt that the best features of both the automated and manually generated 741 documents have been incorporated. Automation of the source data for 741 shipping documents produces greater efficiency while reducing possible errors. Through utilization of the standard DOE/NRC form, continuity within the NMMSS system is maintained, thus minimizing the confusion and redundancy associated with facsimiles. OASIS now fulfills the original concept of near real-time accountability by furnishing a viable 741 document as a function of updating the inventory
High-throughput mouse genotyping using robotics automation.

Science.gov (United States)

Linask, Kaari L; Lo, Cecilia W

2005-02-01

The use of mouse models is rapidly expanding in biomedical research. This has dictated the need for the rapid genotyping of mutant mouse colonies for more efficient utilization of animal holding space. We have established a high-throughput protocol for mouse genotyping using two robotics workstations: a liquid-handling robot to assemble PCR and a microfluidics electrophoresis robot for PCR product analysis. This dual-robotics setup incurs lower start-up costs than a fully automated system while still minimizing human intervention. Essential to this automation scheme is the construction of a database containing customized scripts for programming the robotics workstations. Using these scripts and the robotics systems, multiple combinations of genotyping reactions can be assembled simultaneously, allowing even complex genotyping data to be generated rapidly with consistency and accuracy. A detailed protocol, database, scripts, and additional background information are available at http://dir.nhlbi.nih.gov/labs/ldb-chd/autogene/.
ORIGAMI Automator Primer. Automated ORIGEN Source Terms and Spent Fuel Storage Pool Analysis

Energy Technology Data Exchange (ETDEWEB)

Wieselquist, William A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Thompson, Adam B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bowman, Stephen M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Peterson, Joshua L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-04-01

Source terms and spent nuclear fuel (SNF) storage pool decay heat load analyses for operating nuclear power plants require a large number of Oak Ridge Isotope Generation and Depletion (ORIGEN) calculations. SNF source term calculations also require a significant amount of bookkeeping to track quantities such as core and assembly operating histories, spent fuel pool (SFP) residence times, heavy metal masses, and enrichments. The ORIGEN Assembly Isotopics (ORIGAMI) module in the SCALE code system provides a simple scheme for entering these data. However, given the large scope of the analysis, extensive scripting is necessary to convert formats and process data to create thousands of ORIGAMI input files (one per assembly) and to process the results into formats readily usable by follow-on analysis tools. This primer describes a project within the SCALE Fulcrum graphical user interface (GUI) called ORIGAMI Automator that was developed to automate the scripting and bookkeeping in large-scale source term analyses. The ORIGAMI Automator enables the analyst to (1) easily create, view, and edit the reactor site and assembly information, (2) automatically create and run ORIGAMI inputs, and (3) analyze the results from ORIGAMI. ORIGAMI Automator uses the standard ORIGEN binary concentrations files produced by ORIGAMI, with concentrations available at all time points in each assembly’s life. The GUI plots results such as mass, concentration, activity, and decay heat using a powerful new ORIGEN Post-Processing Utility for SCALE (OPUS) GUI component. This document includes a description and user guide for the GUI, a step-by-step tutorial for a simplified scenario, and appendices that document the file structures used.
Radioanalytical Chemistry for Automated Nuclear Waste Process Monitoring

International Nuclear Information System (INIS)

Jay W. Grate; Timothy A. DeVol

2006-01-01

The objectives of our research were to develop the first automated radiochemical process analyzer including sample pretreatment methodology, and to initiate work on new detection approaches, especially using modified diode detectors
Nuclear power plant personnel qualifications and training. TSORT: an automated technique to assign tasks to training strategies. Volume 1

International Nuclear Information System (INIS)

Jorgensen, C.C.

1984-10-01

This report discusses TSORT, a technique to assist the Nuclear Regulatory Commission (NRC) in evaluating whether training program developers have allocated nuclear power plant tasks to appropriate training strategies. The TSORT structure is presented including training categories selected, dimensions of task information considered, measurement metrics used, and a guide to application. TSORT is implemented as an automated software tool for an IBM-PC. It uses full color graphics and interactive menu selection to provide NRC with a variety of evaluation options including: rank ordering of training strategies reasonable for each task, rank ordering of tasks within strategies, and a variety of special analyses. The program code is also presented along with a comprehensive example of 20 realistic tasks illustrating each of 17 options available
Automated Online Solid-Phase Derivatization for Sensitive Quantification of Endogenous S-Nitrosoglutathione and Rapid Capture of Other Low-Molecular-Mass S-Nitrosothiols.

Science.gov (United States)

Wang, Xin; Garcia, Carlos T; Gong, Guanyu; Wishnok, John S; Tannenbaum, Steven R

2018-02-06

S-Nitrosothiols (RSNOs) constitute a circulating endogenous reservoir of nitric oxide and have important biological activities. In this study, an online coupling of solid-phase derivatization (SPD) with liquid chromatography-mass spectrometry (LC-MS) was developed and applied in the analysis of low-molecular-mass RSNOs. A derivatizing-reagent-modified polymer monolithic column was prepared and adapted for online SPD-LC-MS. Analytes from the LC autosampler flowed through the monolithic column for derivatization and then directly into the LC-MS for analysis. This integration of the online derivatization, LC separation, and MS detection facilitated system automation, allowing rapid, laborsaving, and sensitive detection of RSNOs. S-Nitrosoglutathione (GSNO) was quantified using this automated online method with good linearity (R 2 = 0.9994); the limit of detection was 0.015 nM. The online SPD-LC-MS method has been used to determine GSNO levels in mouse samples, 138 ± 13.2 nM of endogenous GSNO was detected in mouse plasma. Besides, the GSNO concentrations in liver (64.8 ± 11.3 pmol/mg protein), kidney (47.2 ± 6.1 pmol/mg protein), heart (8.9 ± 1.8 pmol/mg protein), muscle (1.9 ± 0.3 pmol/mg protein), hippocampus (5.3 ± 0.9 pmol/mg protein), striatum (6.7 ± 0.6 pmol/mg protein), cerebellum (31.4 ± 6.5 pmol/mg protein), and cortex (47.9 ± 4.6 pmol/mg protein) were also successfully quantified. When the derivatization was performed within 8 min, followed by LC-MS detection, samples could be rapidly analyzed compared with the offline manual method. Other low-molecular-mass RSNOs, such as S-nitrosocysteine and S-nitrosocysteinylglycine, were captured by rapid precursor-ion scanning, showing that the proposed method is a potentially powerful tool for capture, identification, and quantification of RSNOs in biological samples.
Federal Automated Information System of Nuclear Material Control and Accounting: Uniform System of Reporting Documents

International Nuclear Information System (INIS)

Pitel, M V; Kasumova, L; Babcock, R A; Heinberg, C

2003-01-01

One of the fundamental regulations of the Russian State System for Nuclear Material Accounting and Control (SSAC), ''Basic Nuclear Material Control and Accounting Rules,'' directed that a uniform report system be developed to support the operation of the SSAC. According to the ''Regulation on State Nuclear Material Control and Accounting,'' adopted by the Russian Federation Government, Minatom of Russia is response for the development and adoption of report forms, as well as the reporting procedure and schedule. The report forms are being developed in tandem with the creation of an automated national nuclear material control and accounting system, the Federal Information System (FIS). The forms are in different stages of development and implementation. The first report forms (the Summarized Inventory Listing (SIL), Summarized Inventory Change Report (SICR) and federal and agency registers of nuclear material) have already been created and implemented. The second set of reports (nuclear material movement reports and the special anomaly report) is currently in development. A third set of reports (reports on import/export operations, and foreign nuclear material temporarily located in the Russian Federation) is still in the conceptual stage. To facilitate the development of a unified document system, the FIS must establish a uniform philosophy for the reporting system and determine the requirements for each reporting level, adhering to the following principles: completeness--the unified report system provides the entire range of information that the FIS requires to perform SSAC tasks; requisite level of detail; hierarchical structure--each report is based on the information provided in a lower-level report and is the source of information for reports at the next highest level; consistency checking--reports can be checked against other reports. A similar philosophy should eliminate redundancy in the different reports, support a uniform approach to the contents of
High throughput automated microbial bioreactor system used for clone selection and rapid scale-down process optimization.

Science.gov (United States)

Velez-Suberbie, M Lourdes; Betts, John P J; Walker, Kelly L; Robinson, Colin; Zoro, Barney; Keshavarz-Moore, Eli

2018-01-01

High throughput automated fermentation systems have become a useful tool in early bioprocess development. In this study, we investigated a 24 x 15 mL single use microbioreactor system, ambr 15f, designed for microbial culture. We compared the fed-batch growth and production capabilities of this system for two Escherichia coli strains, BL21 (DE3) and MC4100, and two industrially relevant molecules, hGH and scFv. In addition, different carbon sources were tested using bolus, linear or exponential feeding strategies, showing the capacity of the ambr 15f system to handle automated feeding. We used power per unit volume (P/V) as a scale criterion to compare the ambr 15f with 1 L stirred bioreactors which were previously scaled-up to 20 L with a different biological system, thus showing a potential 1,300 fold scale comparability in terms of both growth and product yield. By exposing the cells grown in the ambr 15f system to a level of shear expected in an industrial centrifuge, we determined that the cells are as robust as those from a bench scale bioreactor. These results provide evidence that the ambr 15f system is an efficient high throughput microbial system that can be used for strain and molecule selection as well as rapid scale-up. © 2017 The Authors Biotechnology Progress published by Wiley Periodicals, Inc. on behalf of American Institute of Chemical Engineers Biotechnol. Prog., 34:58-68, 2018. © 2017 The Authors Biotechnology Progress published by Wiley Periodicals, Inc. on behalf of American Institute of Chemical Engineers.
Rapid screening for nuclear genes mutations in isolated respiratory chain complex I defects.

Science.gov (United States)

Pagniez-Mammeri, Hélène; Lombes, Anne; Brivet, Michèle; Ogier-de Baulny, Hélène; Landrieu, Pierre; Legrand, Alain; Slama, Abdelhamid

2009-04-01

Complex I or reduced nicotinamide adenine dinucleotide (NADH): ubiquinone oxydoreductase deficiency is the most common cause of respiratory chain defects. Molecular bases of complex I deficiencies are rarely identified because of the dual genetic origin of this multi-enzymatic complex (nuclear DNA and mitochondrial DNA) and the lack of phenotype-genotype correlation. We used a rapid method to screen patients with isolated complex I deficiencies for nuclear genes mutations by Surveyor nuclease digestion of cDNAs. Eight complex I nuclear genes, among the most frequently mutated (NDUFS1, NDUFS2, NDUFS3, NDUFS4, NDUFS7, NDUFS8, NDUFV1 and NDUFV2), were studied in 22 cDNA fragments spanning their coding sequences in 8 patients with a biochemically proved complex I deficiency. Single nucleotide polymorphisms and missense mutations were detected in 18.7% of the cDNA fragments by Surveyor nuclease treatment. Molecular defects were detected in 3 patients. Surveyor nuclease screening is a reliable method for genotyping nuclear complex I deficiencies, easy to interpret, and limits the number of sequence reactions. Its use will enhance the possibility of prenatal diagnosis and help us for a better understanding of complex I molecular defects.
10 CFR 1017.28 - Processing on Automated Information Systems (AIS).

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Processing on Automated Information Systems (AIS). 1017.28... UNCLASSIFIED CONTROLLED NUCLEAR INFORMATION Physical Protection Requirements § 1017.28 Processing on Automated Information Systems (AIS). UCNI may be processed or produced on any AIS that complies with the guidance in OMB...

Research of the application of the new communication technologies for distribution automation

Science.gov (United States)

Zhong, Guoxin; Wang, Hao

2018-03-01

Communication network is a key factor of distribution automation. In recent years, new communication technologies for distribution automation have a rapid development in China. This paper introduces the traditional communication technologies of distribution automation and analyse the defects of these traditional technologies. Then this paper gives a detailed analysis on some new communication technologies for distribution automation including wired communication and wireless communication and then gives an application suggestion of these new technologies.
Status of automated tensile machine

International Nuclear Information System (INIS)

Satou, M.; Hamilton, M.L.; Sato, S.; Kohyama, A.

1992-01-01

The objective of this work is to develop the Monbusho Automated Tensile machine (MATRON) and install and operate it at the Pacific Northwest Laboratory (PNL). The machine is designed to provide rapid, automated testing of irradiated miniature tensile specimen in a vacuum at elevated temperatures. The MATRON was successfully developed and shipped to PNL for installation in a hot facility. The original installation plan was modified to simplify the current and subsequent installations, and the installation was completed. Detailed procedures governing the operation of the system were written. Testing on irradiated miniature tensile specimen should begin in the near future
Silencing p110β prevents rapid depletion of nuclear pAkt

International Nuclear Information System (INIS)

Ye, Zhi-wei; Ghalali, Aram; Högberg, Johan; Stenius, Ulla

2011-01-01

Highlights: ► p110β was essential for the statin- and ATP-induced depletion of nuclear pAkt and an associated inhibition of growth. ► p110β knock-out inhibited statin-induced changes in binding between FKBP51, pAkt and PTEN. ► Data supports the hypothesis that nuclear pAkt is important for anti-cancer effects of statins. -- Abstract: The p110β subunit in the class IA PI3K family may act as an oncogene and is critical for prostate tumor development in PTEN knockout mice. We tested the possible involvement of p110β in a recently described rapid depletion of phosphorylated Akt (pAkt) in the nucleus. Previous work showed that this down-regulation is induced by extracellular ATP or by statins and is mediated by the purinergic receptor P2X7. Here, we used p110β knock out mouse embryonic fibroblasts (MEFs) and siRNA-treated cancer cells. We found that p110β is essential for ATP- or statin-induced nuclear pAkt depletion in MEFs and in several cancer cell lines including prostate cancer cells. ATP, statin or the selective P2X7 agonist BzATP also inhibited cell growth, and this inhibition was not seen in p110β knock out cells. We also found that p110β was necessary for statin-induced changes in binding between FKBP51, pAkt and PTEN. Our data show that p110β is essential for the ATP- and statin-induced effects and support a role of nuclear pAkt in cancer development. They also provide support for a chemopreventive effect of statins mediated by depletion of nuclear pAkt.
Silencing p110{beta} prevents rapid depletion of nuclear pAkt

Energy Technology Data Exchange (ETDEWEB)

Ye, Zhi-wei; Ghalali, Aram; Hoegberg, Johan [Institute of Environmental Medicine, Karolinska Institutet, S-17177 Stockholm (Sweden); Stenius, Ulla, E-mail: ulla.stenius@ki.se [Institute of Environmental Medicine, Karolinska Institutet, S-17177 Stockholm (Sweden)

2011-12-02

Highlights: Black-Right-Pointing-Pointer p110{beta} was essential for the statin- and ATP-induced depletion of nuclear pAkt and an associated inhibition of growth. Black-Right-Pointing-Pointer p110{beta} knock-out inhibited statin-induced changes in binding between FKBP51, pAkt and PTEN. Black-Right-Pointing-Pointer Data supports the hypothesis that nuclear pAkt is important for anti-cancer effects of statins. -- Abstract: The p110{beta} subunit in the class IA PI3K family may act as an oncogene and is critical for prostate tumor development in PTEN knockout mice. We tested the possible involvement of p110{beta} in a recently described rapid depletion of phosphorylated Akt (pAkt) in the nucleus. Previous work showed that this down-regulation is induced by extracellular ATP or by statins and is mediated by the purinergic receptor P2X7. Here, we used p110{beta} knock out mouse embryonic fibroblasts (MEFs) and siRNA-treated cancer cells. We found that p110{beta} is essential for ATP- or statin-induced nuclear pAkt depletion in MEFs and in several cancer cell lines including prostate cancer cells. ATP, statin or the selective P2X7 agonist BzATP also inhibited cell growth, and this inhibition was not seen in p110{beta} knock out cells. We also found that p110{beta} was necessary for statin-induced changes in binding between FKBP51, pAkt and PTEN. Our data show that p110{beta} is essential for the ATP- and statin-induced effects and support a role of nuclear pAkt in cancer development. They also provide support for a chemopreventive effect of statins mediated by depletion of nuclear pAkt.
XVI International symposium on nuclear electronics and VI International school on automation and computing in nuclear physics and astrophysics; XVI Mezhdunarodnyj simpozium po yadernoj ehlektronike i VI Mezhdunarodnaya shkola po avtomatizatsii issledovanij v yadernoj fizike i astrofizike

Energy Technology Data Exchange (ETDEWEB)

Churin, I N [ed.

1996-12-31

Reports and papers of the 16- International Symposium on nuclear electronics and the 6- International school on automation and computing in nuclear physics and astrophysics are presented. The latest achievements in the field of development of fact - response electronic circuits designed for detecting and spectrometric facilities are studied. The peculiar attention is paid to the systems for acquisition, processing and storage of experimental data. The modern equipment designed for data communication in the computer networks is studied.
Automation of Electrical Cable Harnesses Testing

Directory of Open Access Journals (Sweden)

Zhuming Bi

2017-12-01

Full Text Available Traditional automated systems, such as industrial robots, are applied in well-structured environments, and many automated systems have a limited adaptability to deal with complexity and uncertainty; therefore, the applications of industrial robots in small- and medium-sized enterprises (SMEs are very limited. The majority of manual operations in SMEs are too complicated for automation. The rapidly developed information technologies (IT has brought new opportunities for the automation of manufacturing and assembly processes in the ill-structured environments. Note that an automation solution should be designed to meet the given requirements of the specified application, and it differs from one application to another. In this paper, we look into the feasibility of automated testing for electric cable harnesses, and our focus is on some of the generic strategies for the improvement of the adaptability of automation solutions. Especially, the concept of modularization is adopted in developing hardware and software to maximize system adaptability in testing a wide scope of products. A proposed system has been implemented, and the system performances have been evaluated by executing tests on actual products. The testing experiments have shown that the automated system outperformed manual operations greatly in terms of cost-saving, productivity and reliability. Due to the potential of increasing system adaptability and cost reduction, the presented work has its theoretical and practical significance for an extension for other automation solutions in SMEs.
Intercenter validation of a knowledge based model for automated planning of volumetric modulated arc therapy for prostate cancer. The experience of the German RapidPlan Consortium.

Directory of Open Access Journals (Sweden)

Carolin Schubert

Full Text Available To evaluate the performance of a model-based optimisation process for volumetric modulated arc therapy applied to prostate cancer in a multicentric cooperative group. The RapidPlan (RP knowledge-based engine was tested for the planning of Volumetric modulated arc therapy with RapidArc on prostate cancer patients. The study was conducted in the frame of the German RapidPlan Consortium (GRC.43 patients from one institute of the GRC were used to build and train a RP model. This was further shared with all members of the GRC plus an external site from a different country to increase the heterogeneity of the patient's sampling. An in silico multicentric validation of the model was performed at planning level by comparing RP against reference plans optimized according to institutional procedures. A total of 60 patients from 7 institutes were used.On average, the automated RP based plans resulted fully consistent with the manually optimised set with a modest tendency to improvement in the medium-to-high dose region. A per-site stratification allowed to identify different patterns of performance of the model with some organs at risk resulting better spared with the manual or with the automated approach but in all cases the RP data fulfilled the clinical acceptability requirements. Discrepancies in the performance were due to different contouring protocols or to different emphasis put in the optimization of the manual cases.The multicentric validation demonstrated that it was possible to satisfactorily optimize with the knowledge based model patients from all participating centres. In the presence of possibly significant differences in the contouring protocols, the automated plans, though acceptable and fulfilling the benchmark goals, might benefit from further fine tuning of the constraints. The study demonstrates that, at least for the case of prostate cancer patients, it is possibile to share models among different clinical institutes in a cooperative
A rapidly negotiable first-stage nuclear freeze

International Nuclear Information System (INIS)

Anon.

1988-01-01

This paper reports on the objective of a nuclear freeze which is to slow down or stop the so-far inexorable development and deployment of more and more (read destructive and deadly) nuclear warheads. The essential notion is not new. The proposed treaty for a comprehensive ban on nuclear tests that was very nearly negotiated in 1959 was perhaps the first serious effort to obtain a nuclear freeze, albeit a partial one. Growing concern about the nuclear arms race has led to greatly increased interest in much broader and more effective freezes. A comprehensive nuclear freeze, one that would stop all stages in the manufacture, testing, and deployment of nuclear warheads, would clearly be very desirable and have a great impact. It would not, however, deal with the other worrisome aspects of nuclear weapons, which is the very large number of such weapons that already exist
Implementing New Methods of Laser Marking of Items in the Nuclear Material Control and Accountability System at SSC RF-IPPE: An Automated Laser Marking System

International Nuclear Information System (INIS)

Regoushevsky, V.I.; Tambovtsev, S.D.; Dvukhsherstnov, V.G.; Efimenko, V.F.; Ilyantsev, A.I.; Russ, G.P. III

2009-01-01

For over ten years SSC RF-IPPE, together with the US DOE National Laboratories, has been working on implementing automated control and accountability methods for nuclear materials and other items. Initial efforts to use adhesive bar codes or ones printed (painted) onto metal revealed that these methods were inconvenient and lacked durability under operational conditions. For NM disk applications in critical stands, there is the additional requirement that labels not affect the neutron characteristics of the critical assembly. This is particularly true for the many stainless-steel clad disks containing highly enriched uranium (HEU) and plutonium that are used at SSC RF-IPPE for modeling nuclear power reactors. In search of an alternate method for labeling these disks, we tested several technological options, including laser marking and two-dimensional codes. As a result, the method of laser coloring was chosen in combination with Data Matrix ECC200 symbology. To implement laser marking procedures for the HEU disks and meet all the nuclear material (NM) handling standards and rules, IPPE staff, with U.S. technical and financial support, implemented an automated laser marking system; there are also specially developed procedures for NM movements during laser marking. For the laser marking station, a Zenith 10F system by Telesis Technologies (10 watt Ytterbium Fiber Laser and Merlin software) is used. The presentation includes a flowchart for the automated system and a list of specially developed procedures with comments. Among other things, approaches are discussed for human-factor considerations. To date, markings have been applied to numerous steel-clad HEU disks, and the work continues. In the future this method is expected to be applied to other MC and A items.
The standard laboratory module approach to automation of the chemical laboratory

International Nuclear Information System (INIS)

Hollen, R.M.; Erkkila, T.H.

1993-01-01

Automation of the technology and practice of environmental laboratory automation has not been as rapid or complete as one might expect. Confined to autosamplers and limited robotic systems, our ability to apply production concepts to environmental analytical analysis is not great. With the impending remediation of our hazardous waste sites in the US, only the application of production chemistry techniques will even begin to provide those responsible with the necessary knowledge to accomplish the cleanup expeditiously and safely. Tightening regulatory requirements have already mandated staggering increases in sampling and characterization needs with the future only guaranteeing greater demands. The Contaminant Analysis Automation Program has been initiated by our government to address these current and future characterization by application of a new robotic paradigm for analytical chemistry. By using standardized modular instruments, named Standard Laboratory Modules, flexible automation systems can rapidly be configured to apply production techniques to our nations environmental problems at-site
Safeguards Automated Facility Evaluation (SAFE) methodology

International Nuclear Information System (INIS)

Chapman, L.D.; Grady, L.M.; Bennett, H.A.; Sasser, D.W.; Engi, D.

1978-08-01

An automated approach to facility safeguards effectiveness evaluation has been developed. This automated process, called Safeguards Automated Facility Evaluation (SAFE), consists of a collection of a continuous stream of operational modules for facility characterization, the selection of critical paths, and the evaluation of safeguards effectiveness along these paths. The technique has been implemented on an interactive computer time-sharing system and makes use of computer graphics for the processing and presentation of information. Using this technique, a comprehensive evaluation of a safeguards system can be provided by systematically varying the parameters that characterize the physical protection components of a facility to reflect the perceived adversary attributes and strategy, environmental conditions, and site operational conditions. The SAFE procedure has broad applications in the nuclear facility safeguards field as well as in the security field in general. Any fixed facility containing valuable materials or components to be protected from theft or sabotage could be analyzed using this same automated evaluation technique
Automation inflicted differences on operator performance in nuclear power plant control rooms

Energy Technology Data Exchange (ETDEWEB)

Andersson, Jonas; Osvalder, A.L. [Chalmers Univ. of Technology, Dept. of Product and Producton Development (Sweden)

2007-03-15

Today it is possible to automate almost any function in a human-machine system. Therefore it is important to find a balance between automation level and the prerequisites for the operator to maintain safe operation. Different human factors evaluation methods can be used to find differences between automatic and manual operations that have an effect on operator performance; e.g. Predictive Human Error Analysis (PHEA), NASA Task Load Index (NASA-TLX), Halden Questionnaire, and Human Error Assessment and Reduction Technique (HEART). Results from an empirical study concerning automation levels, made at Ringhals power plant, showed that factors as time pressure and criticality of the work situation influenced the operator's performance and mental workload more than differences in level of automation. The results indicate that the operator's attention strategies differ between the manual and automatic sequences. Independently of level of automation, it is essential that the operator retains control and situational understanding. When performing a manual task, the operator is 'closer' to the process and in control with sufficient situational understanding. When the level of automation increases, the demands on information presentation increase to ensure safe plant operation. The need for control can be met by introducing 'control gates' where the operator has to accept that the automatic procedures are continuing as expected. Situational understanding can be established by clear information about process status and by continuous feedback. A conclusion of the study was that a collaborative control room environment is important. Rather than allocating functions to either the operator or the system, a complementary strategy should be used. Key parameters to consider when planning the work in the control room are time constraints and task criticality and how they affect the performance of the joint cognitive system.However, the examined working
Automation inflicted differences on operator performance in nuclear power plant control rooms

International Nuclear Information System (INIS)

Andersson, Jonas; Osvalder, A.L.

2007-03-01

Today it is possible to automate almost any function in a human-machine system. Therefore it is important to find a balance between automation level and the prerequisites for the operator to maintain safe operation. Different human factors evaluation methods can be used to find differences between automatic and manual operations that have an effect on operator performance; e.g. Predictive Human Error Analysis (PHEA), NASA Task Load Index (NASA-TLX), Halden Questionnaire, and Human Error Assessment and Reduction Technique (HEART). Results from an empirical study concerning automation levels, made at Ringhals power plant, showed that factors as time pressure and criticality of the work situation influenced the operator's performance and mental workload more than differences in level of automation. The results indicate that the operator's attention strategies differ between the manual and automatic sequences. Independently of level of automation, it is essential that the operator retains control and situational understanding. When performing a manual task, the operator is 'closer' to the process and in control with sufficient situational understanding. When the level of automation increases, the demands on information presentation increase to ensure safe plant operation. The need for control can be met by introducing 'control gates' where the operator has to accept that the automatic procedures are continuing as expected. Situational understanding can be established by clear information about process status and by continuous feedback. A conclusion of the study was that a collaborative control room environment is important. Rather than allocating functions to either the operator or the system, a complementary strategy should be used. Key parameters to consider when planning the work in the control room are time constraints and task criticality and how they affect the performance of the joint cognitive system.However, the examined working situations were too different
WEpods project : Finding the potential for automated road public transport

NARCIS (Netherlands)

Homem De Almeida Rodriguez Correia, G.

2016-01-01

Vehicle automation is developing rapidly, nevertheless a lot of wor k is still lacking, as we are not yet at a point where vehicles are able to drive themselves on a road without a human behind the wheel. One of the possibilities of automation is its use as public transport. In theWEpods project,
Impact of automation on mass spectrometry.

Science.gov (United States)

Zhang, Yan Victoria; Rockwood, Alan

2015-10-23

Mass spectrometry coupled to liquid chromatography (LC-MS and LC-MS/MS) is an analytical technique that has rapidly grown in popularity in clinical practice. In contrast to traditional technology, mass spectrometry is superior in many respects including resolution, specificity, multiplex capability and has the ability to measure analytes in various matrices. Despite these advantages, LC-MS/MS remains high cost, labor intensive and has limited throughput. This specialized technology requires highly trained personnel and therefore has largely been limited to large institutions, academic organizations and reference laboratories. Advances in automation will be paramount to break through this bottleneck and increase its appeal for routine use. This article reviews these challenges, shares perspectives on essential features for LC-MS/MS total automation and proposes a step-wise and incremental approach to achieve total automation through reducing human intervention, increasing throughput and eventually integrating the LC-MS/MS system into the automated clinical laboratory operations. Copyright © 2015 Elsevier B.V. All rights reserved.
Electronic system for the automation of current measurements produced by ionization chambers

International Nuclear Information System (INIS)

Brancaccio, Franco; Dias, Mauro da Silva

2002-01-01

Ionization Chambers in current mode operation are usually used in Nuclear Metrology in the determination of radionuclide activity. For this purpose measurements of very low ionization currents, in the range of 10 -8 to 10 -14 A, are required. Usually, electrometers perform the current integration method under command of signals from an automation system, in order to reduce the measurement uncertainties. In the present work, an automation system, developed for current integration measurements at the Laboratorio de Metrologia Nuclear (LMN) of Instituto de Pesquisas Energeticas e Nucleares (IPEN), is described. This automation system is composed by software (graphic interface and control) and an electronic module connected to a microcomputer, by means of a commercial data acquisition card CAD12/32 (LYNX Tecnologia Eletronica Ltda.). Measurements, using an electrometer Keithley 616 (Keithley Instruments, Inc) and an ionization chamber IG12/A20 (20 th Century Electronics Ltd.), were performed in order to check the system and for validating the project. (author)
Automated work packages architecture: An initial set of human factors and instrumentation and controls requirements

Energy Technology Data Exchange (ETDEWEB)

Agarwal, Vivek [Idaho National Lab. (INL), Idaho Falls, ID (United States); Oxstrand, Johanna H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Le Blanc, Katya L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-09-01

The work management process in current fleets of national nuclear power plants is so highly dependent on large technical staffs and quality of work instruction, i.e., paper-based, that this puts nuclear energy at somewhat of a long-term economic disadvantage and increase the possibility of human errors. Technologies like mobile portable devices and computer-based procedures can play a key role in improving the plant work management process, thereby increasing productivity and decreasing cost. Automated work packages are a fundamentally an enabling technology for improving worker productivity and human performance in nuclear power plants work activities because virtually every plant work activity is accomplished using some form of a work package. As part of this year’s research effort, automated work packages architecture is identified and an initial set of requirements identified, that are essential and necessary for implementation of automated work packages in nuclear power plants.
Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

Energy Technology Data Exchange (ETDEWEB)

Scibile, L. [ITER Organization, CS 90 046, St. Paul-lez-Durance, Cedex (France); Ambrosino, G. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); De Tommasi, G., E-mail: detommas@unina.i [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); Pironti, A. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy)

2010-07-15

The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.
Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

International Nuclear Information System (INIS)

Scibile, L.; Ambrosino, G.; De Tommasi, G.; Pironti, A.

2010-01-01

The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.
Automated, High Temperature Furnace for Glovebox Operation

International Nuclear Information System (INIS)

Neikirk, K.

2001-01-01

The U.S. Department of Energy will immobilize excess plutonium in the proposed Plutonium Immobilization Plant (PIP) at the Savannah River Site (SRS) as part of a two track approach for the disposition of weapons usable plutonium. As such, the Department of Energy is funding a development and testing effort for the PIP. This effort is being performed jointly by Lawrence Livermore National Laboratory (LLNL), Westinghouse Savannah River Company (WSRC), Pacific Northwest National Laboratory (PNNL), and Argonne National Laboratory (ANL). The Plutonium Immobilization process involves the disposition of excess plutonium by incorporation into ceramic pucks. As part of the immobilization process, furnaces are needed for sintering the ceramic pucks. The furnace being developed for puck sintering is an automated, bottom loaded furnace with insulting package and resistance heating elements located within a nuclear glovebox. Other furnaces considered for the application include retort furnaces and pusher furnaces. This paper, in part, will discuss the furnace technologies considered and furnace technology selected to support reliable puck sintering in a glovebox environment. Due to the radiation levels and contamination associated with the plutonium material, the sintering process will be fully automated and contained within nuclear material gloveboxes. As such, the furnace currently under development incorporates water and air cooling to minimize heat load to the glovebox. This paper will describe the furnace equipment and systems needed to employ a fully automated puck sintering process within nuclear gloveboxes as part of the Plutonium Immobilization Plant

Automation and remote handling activities in BARC: an overview

International Nuclear Information System (INIS)

Badodkar, D.N.

2016-01-01

Division of Remote Handling and Robotics, BARC has been working on design and development of various application specific remote handling and automation systems for nuclear front-end and back-end fuel cycle technologies. Division is also engaged in preservice and in-service inspection of coolant channels for Pressurized Heavy Water Reactors in India. Design and development of Reactor Control Mechanisms for Nuclear Research and Power Reactors (PHWRs and Compact LWRs) is another important activity carried out in this division. Robotic systems for Indoor and Outdoor surveillance in and around nuclear installations have also been developed. A line scan camera based system has been developed for measuring individual PHWR fuel pellet lengths as well as stack length. An industrial robot is used for autonomous exchange of pellets to achieve desired stack length. The system can be extended for active fuel pellets also. An automation system has been conceptualized for remote handling and transfer of spent fuel bundles from storage pool directly to the chopper unit of reprocessing plant. In case of Advanced Heavy Water Reactor which uses mixed oxides of (Th-Pu) and (Th-"2"3"3U ) as fuel, automation system for front-end fuel cycle has been designed, which includes Powder processing and pressing; Pellet handling and inspection; Pin handling and inspection; and Cluster assembly and dis-assembly in shielded facilities. System demonstration through fullscale mock-up facility is nearing completion. Above talk is presented on behalf of all the officers and staff of DRHR. The talk is mainly focused on development of an automated fuel fabrication facility for mixed oxides of (Th- Pu)/(Th-"2"3"3U ) fuel pins. An overview of divisional ongoing activities in the field of remote handling and automation are also covered. (author)
Automated pose estimation of objects using multiple ID devices for handling and maintenance task in nuclear fusion reactor

International Nuclear Information System (INIS)

Umetani, Tomohiro; Morioka, Jun-ichi; Tamura, Yuichi; Inoue, Kenji; Arai, Tatsuo; Mae, Yasusi

2011-01-01

This paper describes a method for the automated estimation of three-dimensional pose (position and orientation) of objects by autonomous robots, using multiple identification (ID) devices. Our goal is to estimate the object pose for assembly or maintenance tasks in a real nuclear fusion reactor system, with autonomous robots cooperating in a virtual assembly system. The method estimates the three-dimensional pose for autonomous robots. This paper discusses a method of motion generation for ID acquisition using the sensory data acquired by the measurement system attached to the robots and from the environment. Experimental results show the feasibility of the proposed method. (author)
Rapid Automated Target Segmentation and Tracking on 4D Data without Initial Contours

International Nuclear Information System (INIS)

Chebrolu, V.V.; Chebrolu, V.V.; Saenz, D.; Tewatia, D.; Paliwal, B.R.; Chebrolu, V.V.; Saenz, D.; Paliwal, B.R.; Sethares, W.A.; Cannon, G.

2014-01-01

To achieve rapid automated delineation of gross target volume (GTV) and to quantify changes in volume/position of the target for radiotherapy planning using four-dimensional (4D) CT. Methods and Materials. Novel morphological processing and successive localization (MPSL) algorithms were designed and implemented for achieving auto segmentation. Contours automatically generated using MPSL method were compared with contours generated using state-of-the-art deformable registration methods (using Elastix © and MIMV ista software). Metrics such as the Dice similarity coefficient, sensitivity, and positive predictive value (PPV) were analyzed. The target motion tracked using the centroid of the GTV estimated using MPSL method was compared with motion tracked using deformable registration methods. Results. MPSL algorithm segmented the GTV in 4DCT images in 27.0 ±11.1 seconds per phase ( 512 ×512 resolution) as compared to 142.3±11.3 seconds per phase for deformable registration based methods in 9 cases. Dice coefficients between MPSL generated GTV contours and manual contours (considered as ground-truth) were 0.865 ± 0.037. In comparison, the Dice coefficients between ground-truth and contours generated using deformable registration based methods were 0.909 ± 0.051. Conclusions. The MPSL method achieved similar segmentation accuracy as compared to state-of-the-art deformable registration based segmentation methods, but with significant reduction in time required for GTV segmentation.
Rapid Automated Target Segmentation and Tracking on 4D Data without Initial Contours

Directory of Open Access Journals (Sweden)

Venkata V. Chebrolu

2014-01-01

Full Text Available Purpose. To achieve rapid automated delineation of gross target volume (GTV and to quantify changes in volume/position of the target for radiotherapy planning using four-dimensional (4D CT. Methods and Materials. Novel morphological processing and successive localization (MPSL algorithms were designed and implemented for achieving autosegmentation. Contours automatically generated using MPSL method were compared with contours generated using state-of-the-art deformable registration methods (using Elastix© and MIMVista software. Metrics such as the Dice similarity coefficient, sensitivity, and positive predictive value (PPV were analyzed. The target motion tracked using the centroid of the GTV estimated using MPSL method was compared with motion tracked using deformable registration methods. Results. MPSL algorithm segmented the GTV in 4DCT images in 27.0±11.1 seconds per phase (512×512 resolution as compared to 142.3±11.3 seconds per phase for deformable registration based methods in 9 cases. Dice coefficients between MPSL generated GTV contours and manual contours (considered as ground-truth were 0.865±0.037. In comparison, the Dice coefficients between ground-truth and contours generated using deformable registration based methods were 0.909 ± 0.051. Conclusions. The MPSL method achieved similar segmentation accuracy as compared to state-of-the-art deformable registration based segmentation methods, but with significant reduction in time required for GTV segmentation.
Rapid Automated Target Segmentation and Tracking on 4D Data without Initial Contours.

Science.gov (United States)

Chebrolu, Venkata V; Saenz, Daniel; Tewatia, Dinesh; Sethares, William A; Cannon, George; Paliwal, Bhudatt R

2014-01-01

Purpose. To achieve rapid automated delineation of gross target volume (GTV) and to quantify changes in volume/position of the target for radiotherapy planning using four-dimensional (4D) CT. Methods and Materials. Novel morphological processing and successive localization (MPSL) algorithms were designed and implemented for achieving autosegmentation. Contours automatically generated using MPSL method were compared with contours generated using state-of-the-art deformable registration methods (using Elastix© and MIMVista software). Metrics such as the Dice similarity coefficient, sensitivity, and positive predictive value (PPV) were analyzed. The target motion tracked using the centroid of the GTV estimated using MPSL method was compared with motion tracked using deformable registration methods. Results. MPSL algorithm segmented the GTV in 4DCT images in 27.0 ± 11.1 seconds per phase (512 × 512 resolution) as compared to 142.3 ± 11.3 seconds per phase for deformable registration based methods in 9 cases. Dice coefficients between MPSL generated GTV contours and manual contours (considered as ground-truth) were 0.865 ± 0.037. In comparison, the Dice coefficients between ground-truth and contours generated using deformable registration based methods were 0.909 ± 0.051. Conclusions. The MPSL method achieved similar segmentation accuracy as compared to state-of-the-art deformable registration based segmentation methods, but with significant reduction in time required for GTV segmentation.
Monitored Retrievable Storage/Multi-Purpose Canister analysis: Simulation and economics of automation

International Nuclear Information System (INIS)

Bennett, P.C.; Stringer, J.B.

1994-01-01

Robotic automation is examined as a possible alternative to manual spent nuclear fuel, transport cask and Multi-Purpose canister (MPC) handling at a Monitored Retrievable Storage (MRS) facility. Automation of key operational aspects for the MRS/MPC system are analyzed to determine equipment requirements, through-put times and equipment costs is described. The economic and radiation dose impacts resulting from this automation are compared to manual handling methods
Visual interface for the automation of the instrumented pendulum of Charpy tests used in the surveillance program of reactors vessel of nuclear power plants

International Nuclear Information System (INIS)

Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A.

2004-01-01

Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)
Automation in nuclear hot cells (Paper No. 020)

International Nuclear Information System (INIS)

Pal, B.C.; Chougule, A.S.; Radke, M.G.; Ramaswamy, N.V.; Ramkumar, M.S.

1987-02-01

Bhabha Atomic Research Centre (BARC) in Trombay produces radioactive sources for a wide variety of uses in industry, agriculture and medicine, both within the country and abroad. The production and delivery of the radioactive sources in a form, ready for the end use, entails a number of operations, most of which are to be done with remote handling facilities, to maintain the prescribed biological shield to protect the operators. One of the repetitive operation among these which has to be done inside a concrete shielded hot-cell is the picking up of tiny radioactive wafers of iridium as small as 2.5mm dia., 0.3mm thick placing them in the required numbers to make up the total activity inside a capsule, closing the capsule with a top lid and finally welding the capsule. For doing this job remotely, recourse had to be taken to the use of master-slave manipulators (MSM), needing highly skilled operators to handle it for such delicate jobs repetitively. The operations for this repetitive job unlike most of other hot-cell operations, can be structured for machine operation and also fully automated. An automated system synthesising electromechanical, pneumatic and welding operations developed by the Division of Remote Handling and Robotics, BARC is described here. This relieves the operator of a number of jobs, to be repetitively done by MSM which would be strenous and taxing on account of the extremely small sizes of the pellets and wafers when they are to be handled, by remote indirect means with reliance on the master slave manipulators. A description of the automated system is given. (author). 3 figs
Diagnostic system for the nuclear medicine with baby cyclotron

International Nuclear Information System (INIS)

Kashihara, Masao; Wakasa, Shyuichiro

1982-01-01

The system of cyclotron nuclear medicine consists of ''RI-production by using the cyclotron'', ''production of radio-pharmaceuticals labeled with RI'', ''positron tomography''. On the other hand, Ultra compact cyclotron (Baby cyclotron) itself, RI production technique and positron tomography have been rapidly developed and advanced. We think that these three functions must be balance in the development in order to spread this system into the routine work in the hospital. However, since the technology of the synthesis for the labeled compounds is not so developed so far, more advance can be strongly expected. In this report, construction of the cyclotron nuclear medicine, utility for the practical use of RI produced by using the cyclotron, technique of RI production, and the studies on automated and efficient productions of radio-pharmaceuticals labeled with short-lived positron emitters for medical diagnostic use are described. (author)
A new assay for cytotoxic lymphocytes, based on a radioautographic readout of 111In release, suitable for rapid, semi-automated assessment of limit-dilution cultures

International Nuclear Information System (INIS)

Shortman, K.; Wilson, A.

1981-01-01

A new assay for cytotoxic T lymphocytes is described, of general application, but particularly suitable for rapid, semi-automated assessment of multiple microculture tests. Target cells are labelled with high efficiency and to high specific activity with the oxine chelate of 111 indium. After a 3-4 h incubation of test cells with 5 X 10 3 labelled target cells in V wells of microtitre trays, samples of the supernatant are spotted on paper (5 μl) or transferred to soft-plastic U wells (25-50 μl) and the 111 In release assessed by radioautography. Overnight exposure of X-ray film with intensifying screens at -70 0 C gives an image which is an intense dark spot for maximum release, a barely visible darkening with the low spontaneous release, and a definite positive with 10% specific lysis. The degree of film darkening, which can be quantitated by microdensitometry, shows a linear relationship with cytotoxic T lymphocyte dose up to the 40% lysis level. The labelling intensity and sensitivity can be adjusted over a wide range, allowing a single batch of the short half-life isotope to serve for 2 weeks. The 96 assays from a single tray are developed simultaneously on a single small sheet of film. Many trays can be processed together, and handling is rapid if 96-channel automatic pipettors are used. The method allows rapid visual scanning for positive and negative limit dilution cultures in cytotoxic T cell precursor frequency and specificity studies. In addition, in conjunction with an automated densitometer designed to scan microtitre trays, the method provides an efficient alternative to isotope counting in routine cytotoxic assays. (Auth.)
Development of the RSAC Automation System for Reload Core of WH NPP

International Nuclear Information System (INIS)

Choi, Yu Sun; Bae, Sung Man; Koh, Byung Marn; Hong, Sun Kwan

2006-01-01

The Nuclear Design for Reload Core of Westinghouse Nuclear Power Plant consists of 'Reload Core Model Search', 'Safety Analysis(RSAC)', 'NDR(Nuclear Design Report) and OCAP(Operational Core Analysis Package Generation)' phases. Since scores of calculations for various accidents are required to confirm that the safety analysis assumptions are valid, the Safety Analysis(RSAC) is the most important and time and effort consuming phase of reload core design sequence. The Safety Analysis Automation System supports core designer by the automation of safety analysis calculations in 'Safety Analysis' phase(about 20 calculations). More than 10 kinds of codes, APA(ALPHA/PHOENIX/ANC), APOLLO, VENUS, PHIRE XEFIT, INCORE, etc. are being used for Safety Analysis calculations. Westinghouse code system needs numerous inputs and outputs, so the possibility of human errors could not be ignored during Safety Analysis calculations. To remove these inefficiencies, all input files for Safety Analysis calculations are automatically generated and executed by this Safety Analysis Automation System. All calculation notes are generated and the calculation results are summarized in RSAC (Reload Safety Analysis Checklist) by this system. Therefore, The Safety Analysis Automation System helps the reload core designer to perform safety analysis of the reload core model instantly and correctly
Automatization of welding for nuclear power equipments and facilities

International Nuclear Information System (INIS)

Tamai, Yasumasa; Matsumoto, Teruo; Koyama, Takaichi

1980-01-01

For the requirement of high reliability in the construction of nuclear power plants and the reduction of radiation exposure in the modefying works of existing plants, the automation and remote operation of welding have increased their necessity. In this paper, the present state of the automation of welding for making machines, equipments and pipings for nuclear power plants in Hitachi Ltd. is described, and the aim of developing the automation, the features of the equipments and the state of application to actual plants are introduced, centering around the automation of welding for large structures such as reactor containment vessels and the remote type automatic welding system for pipings. By these automations, the large outcomes were obtained in the improvement of welding quality required for the machines and equipments for atomic energy. Moreover, the conspicuous results were also obtained in case of the peculiar works to nuclear power plants, in which the reduction of the radiation exposure related to human bodies and the welding of high quality are demanded. The present state of the automation of welding for nuclear installations in Hitachi Ltd., the development of automatic welding equipments and the present state of application to actual plants, and the development and application of the automatic pipe working machine for reducing radiation exposure are explained. (Kako, I.)
High-throughput microfluidics automated cytogenetic processing for effectively lowering biological process time and aid triage during radiation accidents

International Nuclear Information System (INIS)

Ramakumar, Adarsh

2016-01-01

Nuclear or radiation mass casualties require individual, rapid, and accurate dose-based triage of exposed subjects for cytokine therapy and supportive care, to save life. Radiation mass casualties will demand high-throughput individual diagnostic dose assessment for medical management of exposed subjects. Cytogenetic techniques are widely used for triage and definitive radiation biodosimetry. Prototype platform to demonstrate high-throughput microfluidic micro incubation to support the logistics of sample in miniaturized incubators from the site of accident to analytical labs has been developed. Efforts have been made, both at the level of developing concepts and advanced system for higher throughput in processing the samples and also implementing better and efficient methods of logistics leading to performance of lab-on-chip analyses. Automated high-throughput platform with automated feature extraction, storage, cross platform data linkage, cross platform validation and inclusion of multi-parametric biomarker approaches will provide the first generation high-throughput platform systems for effective medical management, particularly during radiation mass casualty events
Challenges when bringing IoT into Industrial Automation

OpenAIRE

Lennvall, Tomas; Gidlund, Mikael; Åkerberg, Johan

2017-01-01

The Internet of Things (IoT) is captivating the society because of its potential to rapidly transform businesses and people’s lives. It is widely believed that IoT will also transform the industrial automation business in terms of improved productivity, less cost, flexibility, and increased revenues. Hence, there are some challenges that needs to be addressed when IoT is introduced to the industrial automation domain. This paperaims to present realistic requirements and highlights identified ...
AP600 level of automation: United States utility perspective

International Nuclear Information System (INIS)

Bekkerman, A.Y.

1997-01-01

Design of the AP600 advanced nuclear plant man-machine interface system (M-MIS) is guided by the applicable requirements from the Utility Requirements Document (URD). However, the URD has left certain aspects of the M-MIS to be determined by the designer working together with utilities sponsoring the work. This is particularly true in the case of the level of automation to be designed into the M-MIS. Based on experience from currently operating plants, utilities have specified the identity and roles of personnel in the control room, which has led to establishing a number of level of automation issues for the AP600. The key role of automated computerized procedures in the AP600 automation has been determined and resolved. 5 refs
A Project in Support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Ko, Young Cheol; Kim, Kyoung Pyo; Yi, Ji Ho [and others

2007-12-15

The results and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy information and computer software developed in the advanced countries.
A Project in Support of Nuclear Technology Cooperation

International Nuclear Information System (INIS)

Ko, Young Cheol; Kim, Kyoung Pyo; Yi, Ji Ho

2007-12-01

The results and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy information and computer software developed in the advanced countries
A Project in Support of Nuclear Technology Cooperation

Energy Technology Data Exchange (ETDEWEB)

Ko, Young Cheol; Kim, Kyoung Pyo; Yi, Ji Ho (and others)

2007-12-15

The results and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy information and computer software developed in the advanced countries.
Assessment of Automated Data Analysis Application on VVER Steam Generator Tubing

International Nuclear Information System (INIS)

Picek, E.; Barilar, D.

2006-01-01

INETEC - Institute for Nuclear Technology has developed software package named EddyOne having an option of automated analysis of bobbin coil eddy current data. During its development and site use some features were noticed preventing the wide use automatic analysis on VVER SG data. This article discuss these specific problems as well evaluates possible solutions. With regards to current state of automated analysis technology an overview of advantaged and disadvantages of automated analysis on VVER SG is summarized as well.(author)
Inventory management and reagent supply for automated chemistry.

Science.gov (United States)

Kuzniar, E

1999-08-01

Developments in automated chemistry have kept pace with developments in HTS such that hundreds of thousands of new compounds can be rapidly synthesized in the belief that the greater the number and diversity of compounds that can be screened, the more successful HTS will be. The increasing use of automation for Multiple Parallel Synthesis (MPS) and the move to automated combinatorial library production is placing an overwhelming burden on the management of reagents. Although automation has improved the efficiency of the processes involved in compound synthesis, the bottleneck has shifted to ordering, collating and preparing reagents for automated chemistry resulting in loss of time, materials and momentum. Major efficiencies have already been made in the area of compound management for high throughput screening. Most of these efficiencies have been achieved with sophisticated library management systems using advanced engineering and data handling for the storage, tracking and retrieval of millions of compounds. The Automation Partnership has already provided many of the top pharmaceutical companies with modular automated storage, preparation and retrieval systems to manage compound libraries for high throughput screening. This article describes how these systems may be implemented to solve the specific problems of inventory management and reagent supply for automated chemistry.

Automated contamination monitoring for hot particles

International Nuclear Information System (INIS)

Johnstone, G.; Case, L.

1987-01-01

INS Corp., the largest nuclear laundry company in the United States, has recently developed two types of automated contamination monitoring systems: 1) the Automated Laundry Monitor (ALM), which provides quality assurance monitoring for protective clothing contamination and 2) a low-level automated monitoring system for Plastic Volume Reduction Service (PVRS). The presentation details the inaccuracies associated with hand-probe frisking which led to the development of the ALM. The ALM was designed for 100% quality assurance monitoring of garments to the most stringent customer requirements. A review of why the ALM is essential in verifying the absence of hot particles on garments is given. The final topic addresses the expansion of the ALM technology in support of the INS Plastic Volume Reduction Service by monitoring decontaminated plastics to free release levels. This presentation reviews the design and operation of both monitoring systems
Changing technology in transportation : automated vehicles in freight.

Science.gov (United States)

2017-06-27

The world of transportation is on the verge of undergoing an impactful transformation. Over the past decade, automotive computing technology has progressed far more rapidly than anticipated. Most major auto manufacturers integrated automated features...
Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

Energy Technology Data Exchange (ETDEWEB)

Rahman, Nur Aira Abd, E-mail: nur-aira@nuclearmalaysia.gov.my; Yussup, Nolida; Ibrahim, Maslina Bt. Mohd; Mokhtar, Mukhlis B.; Soh Shaari, Syirrazie Bin Che; Azman, Azraf B. [Technical Support Division, Malaysian Nuclear Agency, 43000, Kajang, Selangor (Malaysia); Salim, Nazaratul Ashifa Bt. Abdullah [Division of Waste and Environmental Technology, Malaysian Nuclear Agency, 43000, Kajang, Selangor (Malaysia); Ismail, Nadiah Binti [Fakulti Kejuruteraan Elektrik, UiTM Pulau Pinang, 13500 Permatang Pauh, Pulau Pinang (Malaysia)

2015-04-29

Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on ‘Development of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)’. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6.
Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

Science.gov (United States)

Rahman, Nur Aira Abd; Yussup, Nolida; Salim, Nazaratul Ashifa Bt. Abdullah; Ibrahim, Maslina Bt. Mohd; Mokhtar, Mukhlis B.; Soh@Shaari, Syirrazie Bin Che; Azman, Azraf B.; Ismail, Nadiah Binti

2015-04-01

Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on `Development of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)'. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6.
Start up testing for the secure automated fabrication line

International Nuclear Information System (INIS)

Gerber, E.W.; Benson, E.M.; Dahl, R.E.

1986-01-01

The Secure Automated Fabrication (SAF) Line has been designed and built by Westinghouse Hanford Company for the Department of Energy at the Hanford Site near Richland, Washington. The SAF Line will provide the capability for remote manufacture of fuel for Liquid Metal Reactors, and will supply fuel for the Fast Flux Test Facility (FFTF). The SAF process is highly automated and represents a major advancement in nuclear fuel manufacturing, offering significant improvements in product quality, productivity, safety, and accountability of Special Nuclear Materials. The construction phase of the project is complete, and testing has been initiated to accomplish start up of the plant for manufacture of FFTF fuel. This paper describes the test methodology used for SAF Line start up
A Fully Automated High-Throughput Zebrafish Behavioral Ototoxicity Assay.

Science.gov (United States)

Todd, Douglas W; Philip, Rohit C; Niihori, Maki; Ringle, Ryan A; Coyle, Kelsey R; Zehri, Sobia F; Zabala, Leanne; Mudery, Jordan A; Francis, Ross H; Rodriguez, Jeffrey J; Jacob, Abraham

2017-08-01

Zebrafish animal models lend themselves to behavioral assays that can facilitate rapid screening of ototoxic, otoprotective, and otoregenerative drugs. Structurally similar to human inner ear hair cells, the mechanosensory hair cells on their lateral line allow the zebrafish to sense water flow and orient head-to-current in a behavior called rheotaxis. This rheotaxis behavior deteriorates in a dose-dependent manner with increased exposure to the ototoxin cisplatin, thereby establishing itself as an excellent biomarker for anatomic damage to lateral line hair cells. Building on work by our group and others, we have built a new, fully automated high-throughput behavioral assay system that uses automated image analysis techniques to quantify rheotaxis behavior. This novel system consists of a custom-designed swimming apparatus and imaging system consisting of network-controlled Raspberry Pi microcomputers capturing infrared video. Automated analysis techniques detect individual zebrafish, compute their orientation, and quantify the rheotaxis behavior of a zebrafish test population, producing a powerful, high-throughput behavioral assay. Using our fully automated biological assay to test a standardized ototoxic dose of cisplatin against varying doses of compounds that protect or regenerate hair cells may facilitate rapid translation of candidate drugs into preclinical mammalian models of hearing loss.
A Toolset for Supporting Iterative Human Automation: Interaction in Design

Science.gov (United States)

Feary, Michael S.

2010-01-01

The addition of automation has greatly extended humans' capability to accomplish tasks, including those that are difficult, complex and safety critical. The majority of Human - Automation Interacton (HAl) results in more efficient and safe operations, ho,,:,ever ertain unpected atomatlon behaviors or "automation surprises" can be frustrating and, In certain safety critical operations (e.g. transporttion, manufacturing control, medicine), may result in injuries or. the loss of life.. (Mellor, 1994; Leveson, 1995; FAA, 1995; BASI, 1998; Sheridan, 2002). This papr describes he development of a design tool that enables on the rapid development and evaluation. of automaton prototypes. The ultimate goal of the work is to provide a design platform upon which automation surprise vulnerability analyses can be integrated.
Integrated safeguards and security for a highly automated process

International Nuclear Information System (INIS)

Zack, N.R.; Hunteman, W.J.; Jaeger, C.D.

1993-01-01

Before the cancellation of the New Production Reactor Programs for the production of tritium, the reactors and associated processing were being designed to contain some of the most highly automated and remote systems conceived for a Department of Energy facility. Integrating safety, security, materials control and accountability (MC and A), and process systems at the proposed facilities would enhance the overall information and protection-in-depth available. Remote, automated fuel handling and assembly/disassembly techniques would deny access to the nuclear materials while upholding ALARA principles but would also require the full integration of all data/information systems. Such systems would greatly enhance MC and A as well as facilitate materials tracking. Physical protection systems would be connected with materials control features to cross check activities and help detect and resolve anomalies. This paper will discuss the results of a study of the safeguards and security benefits achieved from a highly automated and integrated remote nuclear facility and the impacts that such systems have on safeguards and computer and information security
Development of automated patrol-type monitoring and inspection system for nuclear power plant and application to actual plant

International Nuclear Information System (INIS)

Senoo, Makoto; Koga, Kazunori; Hirakawa, Hiroshi; Tanaka, Keiji

1996-01-01

An automated patrol-type monitoring and inspection system was developed and applied in a nuclear power plant. This system consists of a monorail, a monitoring robot and an operator's console. The monitoring robot consists of a sensor unit and a control unit. Three kinds of sensor, a color ITV camera, an infrared camera and a microphone are installed in the sensor unit. The features of this monitoring robot are; (1) Weights 15 kg with a cross-sectional dimensions of 152 mm width and 290 mm height. (2) Several automatic monitoring functions are installed using image processing and frequency analysis for three sensor signals. (author)
Automated systems for control of technological processes at nuclear power plants and their use in putting the plant into operation

International Nuclear Information System (INIS)

Majtan, L.

1987-01-01

The systems of testing and control of technological processes in WWER-440 units in nuclear power plants which have so far been constructed in Czechoslovakia have been based on the conceptual principles and hardware used in the USSR. For the Mochovce nuclear power plant an automated process control system is to be introduced which proceeds from experiences gained with new Czechoslovak conventional power plants with 200 MW units. The control system consists of two levels: unit control and the control of the whole power plant the unit control consists of the DERIS-900 decentralized control system and the SM 1804 microcomputer and SM 1420 minicomputer based information and control system. A data processing system based on the SM 52/11.M1 minicomputer system will be used for power plant start-up and commissioning. (Z.M.). 2 figs., 4 refs
Laboratory automation: trajectory, technology, and tactics.

Science.gov (United States)

Markin, R S; Whalen, S A

2000-05-01

Laboratory automation is in its infancy, following a path parallel to the development of laboratory information systems in the late 1970s and early 1980s. Changes on the horizon in healthcare and clinical laboratory service that affect the delivery of laboratory results include the increasing age of the population in North America, the implementation of the Balanced Budget Act (1997), and the creation of disease management companies. Major technology drivers include outcomes optimization and phenotypically targeted drugs. Constant cost pressures in the clinical laboratory have forced diagnostic manufacturers into less than optimal profitability states. Laboratory automation can be a tool for the improvement of laboratory services and may decrease costs. The key to improvement of laboratory services is implementation of the correct automation technology. The design of this technology should be driven by required functionality. Automation design issues should be centered on the understanding of the laboratory and its relationship to healthcare delivery and the business and operational processes in the clinical laboratory. Automation design philosophy has evolved from a hardware-based approach to a software-based approach. Process control software to support repeat testing, reflex testing, and transportation management, and overall computer-integrated manufacturing approaches to laboratory automation implementation are rapidly expanding areas. It is clear that hardware and software are functionally interdependent and that the interface between the laboratory automation system and the laboratory information system is a key component. The cost-effectiveness of automation solutions suggested by vendors, however, has been difficult to evaluate because the number of automation installations are few and the precision with which operational data have been collected to determine payback is suboptimal. The trend in automation has moved from total laboratory automation to a
A novel method for rapid comparative quantitative analysis of nuclear fuel cycles

International Nuclear Information System (INIS)

Eastham, Sebastian D.; Coates, David J.; Parks, Geoffrey T.

2012-01-01

Highlights: ► Metric framework determined to compare nuclear fuel cycles. ► Fast and thermal reactors simulated using MATLAB models, including thorium. ► Modelling uses deterministic methods instead of Monte–Carlo for speed. ► Method rapidly identifies relative cycle strengths and weaknesses. ► Significant scope for use in project planning and cycle optimisation. - Abstract: One of the greatest obstacles facing the nuclear industry is that of sustainability, both in terms of the finite reserves of uranium ore and the production of highly radiotoxic spent fuel which presents proliferation and environmental hazards. Alternative nuclear technologies have been suggested as a means of delivering enhanced sustainability with proposals including fast reactors, the use of thorium fuel and tiered fuel cycles. The debate as to which is the most appropriate technology continues, with each fuel system and reactor type delivering specific advantages and disadvantages which can be difficult to compare fairly. This paper demonstrates a framework of performance metrics which, coupled with a first-order lumped reactor model to determine nuclide population balances, can be used to quantify the aforementioned pros and cons for a range of different fuel and reactor combinations. The framework includes metrics such as fuel efficiency, spent fuel toxicity and proliferation resistance, and relative cycle performance is analysed through parallel coordinate plots, yielding a quantitative comparison of disparate cycles.
Rapid and convenient semi-automated microwave-assisted solid-phase synthesis of arylopeptoids

DEFF Research Database (Denmark)

Rasmussen, Jakob Ewald; Boccia, Marcello Massimo; Nielsen, John

2014-01-01

A facile and expedient route to the synthesis of arylopeptoid oligomers (N-alkylated aminomethyl benz-amides) using semi-automated microwave-assisted solid-phase synthesis is presented. The synthesis was optimized for the incorporation of side chains derived from sterically hindered or unreactive...
Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

International Nuclear Information System (INIS)

Zadrazil, J.; Cvan, M.; Strimelsky, V.

1987-01-01

The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)
Large scale oil lease automation and electronic custody transfer

International Nuclear Information System (INIS)

Price, C.R.; Elmer, D.C.

1995-01-01

Typically, oil field production operations have only been automated at fields with long term production profiles and enhanced recovery. The automation generally consists of monitoring and control at the wellhead and centralized facilities. However, Union Pacific Resources Co. (UPRC) has successfully implemented a large scale automation program for rapid-decline primary recovery Austin Chalk wells where purchasers buy and transport oil from each individual wellsite. This project has resulted in two significant benefits. First, operators are using the system to re-engineer their work processes. Second, an inter-company team created a new electronic custody transfer method. This paper will describe: the progression of the company's automation objectives in the area; the field operator's interaction with the system, and the related benefits; the research and development of the new electronic custody transfer method
Single-purpose nuclear medicine instruments

International Nuclear Information System (INIS)

Boucek, J.

Nuclear medicine requires the most up-to-date specialized technical facilities. The paper underlines the factor of reliability in purpose-designed equipment used for basic examinations. The possibility is also discussed of the automation of standard nuclear medicine instruments
Development and evaluation of an automated reflectance microscope system for the petrographic characterization of bituminous coals

Energy Technology Data Exchange (ETDEWEB)

Hoover, D. S.; Davis, A.

1980-10-01

The development of automated coal petrographic techniques will lessen the demands on skilled personnel to do routine work. This project is concerned with the development and successful testing of an instrument which will meet these needs. The fundamental differences in reflectance of the three primary maceral groups should enable their differentiation in an automated-reflectance frequency histogram (reflectogram). Consequently, reflected light photometry was chosen as the method for automating coal petrographic analysis. Three generations of an automated system (called Rapid Scan Versions I, II and III) were developed and evaluated for petrographic analysis. Their basic design was that of a reflected-light microscope photometer with an automatic stage, interfaced with a minicomputer. The hardware elements used in the Rapid Scan Version I limited the system's flexibility and presented problems with signal digitization and measurement precision. Rapid Scan Version II was designed to incorporate a new microscope photometer and computer system. A digital stepping stage was incorporated into the Rapid Scan Version III system. The precision of reflectance determination of this system was found to be +- 0.02 percent reflectance. The limiting factor in quantitative interpretation of Rapid Scan reflectograms is the resolution of reflectance populations of the individual maceral groups. Statistical testing indicated that reflectograms were highly reproducible, and a new computer program, PETAN, was written to interpret the curves for vitrinite reflectance parameters ad petrographic.
Software complex AS (automation of spectrometry). User interface of experiment automation system implementation

International Nuclear Information System (INIS)

Astakhova, N.V.; Beskrovnyj, A.I.; Bogdzel', A.A.; Butorin, P.E.; Vasilovskij, S.G.; Gundorin, N.A.; Zlokazov, V.B.; Kutuzov, S.A.; Salamatin, I.M.; Shvetsov, V.N.

2003-01-01

An instrumental software complex for automation of spectrometry (AS) that enables prompt realization of experiment automation systems for spectrometers, which use data buferisation, has been developed. In the development new methods of programming and building of automation systems together with novel net technologies were employed. It is suggested that programs to schedule and conduct experiments should be based on the parametric model of the spectrometer, the approach that will make it possible to write programs suitable for any FLNP (Frank Laboratory of Neutron Physics) spectrometer and experimental technique applied and use different hardware interfaces for introducing the spectrometric data into the data acquisition system. The article describes the possibilities provided to the user in the field of scheduling and control of the experiment, data viewing, and control of the spectrometer parameters. The possibility of presenting the current spectrometer state, programs and the experimental data in the Internet in the form of dynamically formed protocols and graphs, as well as of the experiment control via the Internet is realized. To use the means of the Internet on the side of the client, applied programs are not needed. It suffices to know how to use the two programs to carry out experiments in the automated mode. The package is designed for experiments in condensed matter and nuclear physics and is ready for using. (author)
Methodologies for rapid evaluation of seismic demand levels in nuclear power plant structures

International Nuclear Information System (INIS)

Manrique, M.; Asfura, A.; Mukhim, G.

1990-01-01

A methodology for rapid assessment of both acceleration spectral peak and 'zero period acceleration' (ZPA) values for virtually any major structure in a nuclear power plant is presented. The methodology is based on spectral peak and ZPA amplification factors, developed from regression analyses of an analytical database. The developed amplification factors are applied to the plant's design ground spectrum to obtain amplified response parameters. A practical application of the methodology is presented. This paper also presents a methodology for calculating acceleration response spectrum curves at any number of desired damping ratios directly from a single known damping ratio spectrum. The methodology presented is particularly useful and directly applicable to older vintage nuclear power plant facilities (i.e. such as those affected by USI A-46). The methodology is based on principles of random vibration theory. The methodology has been implemented in a computer program (SPECGEN). SPECGEN results are compared with results obtained from time history analyses. (orig.)
The knowledge-based off-site emergency response system for a nuclear power plant

International Nuclear Information System (INIS)

Ho, L.W.; Loa, W.W.; Wang, C.L.

1987-01-01

A knowledge-based expert system for a nuclear power plant off-site emergency response system is described. The system incorporates the knowledge about the nuclear power plant behaviours, site environment and site geographic factors, etc. The system is developed using Chinshan nuclear power station of Taipower Company, Taiwan, ROC as a representative model. The objectives of developing this system are to provide an automated intelligent system with functions of accident simulation, prediction and with learning capabilities to supplement the actions of the emergency planners and accident managers in order to protect the plant personnel and the surrounding population, and prevent or mitigate property damages resulting from the plant accident. The system is capable of providing local and national authorities with rapid retrieval data from the site characteristics and accident progression. The system can also provide the framework for allocation of available resources and can handle the uncertainties in data and models

Building of a CAD system for I and C system of nuclear power plant

International Nuclear Information System (INIS)

Ma Zhicai; Zhang Dongsheng

2013-01-01

An I and C database was developed based on the design objects and properties presented in I and C design documents of nuclear power plant. With the database, a rapid-implemented CAD system for I and C engineering was designed and implemented with popular CAD software, AutoCAD and Visio, and desktop database management system, Access, to manage the design data and to automate the composing task for listings, forms and drawings. This system was applied in an engineering project for data management, document generation and drawing aid, and demonstrated its usability and efficiency. (authors)
Development of Nuclear Power Plant Safety Evaluation Method for the Automation Algorithm Application

Energy Technology Data Exchange (ETDEWEB)

Kim, Seung Geun; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

2016-10-15

It is commonly believed that replacing human operators to the automated system would guarantee greater efficiency, lower workloads, and fewer human error. Conventional machine learning techniques are considered as not capable to handle complex situations in NPP. Due to these kinds of issues, automation is not actively adopted although human error probability drastically increases during abnormal situations in NPP due to overload of information, high workload, and short time available for diagnosis. Recently, new machine learning techniques, which are known as ‘deep learning’ techniques have been actively applied to many fields, and the deep learning technique-based artificial intelligences (AIs) are showing better performance than conventional AIs. In 2015, deep Q-network (DQN) which is one of the deep learning techniques was developed and applied to train AI that automatically plays various Atari 2800 games, and this AI surpassed the human-level playing in many kind of games. Also in 2016, ‘Alpha-Go’, which was developed by ‘Google Deepmind’ based on deep learning technique to play the game of Go (i.e. Baduk), was defeated Se-dol Lee who is the World Go champion with score of 4:1. By the effort for reducing human error in NPPs, the ultimate goal of this study is the development of automation algorithm which can cover various situations in NPPs. As the first part, quantitative and real-time NPP safety evaluation method is being developed in order to provide the training criteria for automation algorithm. For that, EWS concept of medical field was adopted, and the applicability is investigated in this paper. Practically, the application of full automation (i.e. fully replaces human operators) may requires much more time for the validation and investigation of side-effects after the development of automation algorithm, and so the adoption in the form of full automation will take long time.
Development of Nuclear Power Plant Safety Evaluation Method for the Automation Algorithm Application

International Nuclear Information System (INIS)

Kim, Seung Geun; Seong, Poong Hyun

2016-01-01

It is commonly believed that replacing human operators to the automated system would guarantee greater efficiency, lower workloads, and fewer human error. Conventional machine learning techniques are considered as not capable to handle complex situations in NPP. Due to these kinds of issues, automation is not actively adopted although human error probability drastically increases during abnormal situations in NPP due to overload of information, high workload, and short time available for diagnosis. Recently, new machine learning techniques, which are known as ‘deep learning’ techniques have been actively applied to many fields, and the deep learning technique-based artificial intelligences (AIs) are showing better performance than conventional AIs. In 2015, deep Q-network (DQN) which is one of the deep learning techniques was developed and applied to train AI that automatically plays various Atari 2800 games, and this AI surpassed the human-level playing in many kind of games. Also in 2016, ‘Alpha-Go’, which was developed by ‘Google Deepmind’ based on deep learning technique to play the game of Go (i.e. Baduk), was defeated Se-dol Lee who is the World Go champion with score of 4:1. By the effort for reducing human error in NPPs, the ultimate goal of this study is the development of automation algorithm which can cover various situations in NPPs. As the first part, quantitative and real-time NPP safety evaluation method is being developed in order to provide the training criteria for automation algorithm. For that, EWS concept of medical field was adopted, and the applicability is investigated in this paper. Practically, the application of full automation (i.e. fully replaces human operators) may requires much more time for the validation and investigation of side-effects after the development of automation algorithm, and so the adoption in the form of full automation will take long time
A project in support of nuclear technology cooperation

International Nuclear Information System (INIS)

Jung, Ki Jung; Choi, Pyong Hoon; Lee, Ji Ho

2003-12-01

Establish strategies of international cooperation in an effort to promote our nation's leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by memeber states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing
General impact of robotics and automation in radiation environments

International Nuclear Information System (INIS)

Meghdari, A.; Salehi, M.

1993-01-01

Robotics and automation systems in nuclear environments require special design considerations. This paper presents an overview of selected robotic systems already designed and developed for use in nuclear applications at some U.S. laboratories. It will further emphasize on tasks identification, operational constraints, special considerations in materials selection, and a general guideline for robotic systems design in radiation environments. (author). 5 refs, 5 figs
Toward designing for trust in database automation

Energy Technology Data Exchange (ETDEWEB)

Duez, P. P.; Jamieson, G. A. [Cognitive Engineering Laboratory, Univ. of Toronto, 5 King' s College Rd., Toronto, Ont. M5S 3G8 (Canada)

2006-07-01

. The connection between an AH for an automated tool and a list of information elements at the three levels of attributional abstraction is then direct, providing a method for satisfying information requirements for appropriate trust in automation. In this paper, we will present our method for developing specific information requirements for an automated tool, based on a formal analysis of that tool and the models presented by Lee and See. We will show an example of the application of the AH to automation, in the domain of relational database automation, and the resulting set of specific information elements for appropriate trust in the automated tool. Finally, we will comment on the applicability of this approach to the domain of nuclear plant instrumentation. (authors)
Toward designing for trust in database automation

International Nuclear Information System (INIS)

Duez, P. P.; Jamieson, G. A.

2006-01-01

. The connection between an AH for an automated tool and a list of information elements at the three levels of attributional abstraction is then direct, providing a method for satisfying information requirements for appropriate trust in automation. In this paper, we will present our method for developing specific information requirements for an automated tool, based on a formal analysis of that tool and the models presented by Lee and See. We will show an example of the application of the AH to automation, in the domain of relational database automation, and the resulting set of specific information elements for appropriate trust in the automated tool. Finally, we will comment on the applicability of this approach to the domain of nuclear plant instrumentation. (authors)
Rapid detection of enterovirus in cerebrospinal fluid by a fully-automated PCR assay is associated with improved management of aseptic meningitis in adult patients.

Science.gov (United States)

Giulieri, Stefano G; Chapuis-Taillard, Caroline; Manuel, Oriol; Hugli, Olivier; Pinget, Christophe; Wasserfallen, Jean-Blaise; Sahli, Roland; Jaton, Katia; Marchetti, Oscar; Meylan, Pascal

2015-01-01

Enterovirus (EV) is the most frequent cause of aseptic meningitis (AM). Lack of microbiological documentation results in unnecessary antimicrobial therapy and hospitalization. To assess the impact of rapid EV detection in cerebrospinal fluid (CSF) by a fully-automated PCR (GeneXpert EV assay, GXEA) on the management of AM. Observational study in adult patients with AM. Three groups were analyzed according to EV documentation in CSF: group A = no PCR or negative PCR (n=17), group B = positive real-time PCR (n = 20), and group C = positive GXEA (n = 22). Clinical, laboratory and health-care costs data were compared. Clinical characteristics were similar in the 3 groups. Median turn-around time of EV PCR decreased from 60 h (IQR (interquartile range) 44-87) in group B to 5h (IQR 4-11) in group C (p<0.0001). Median duration of antibiotics was 1 (IQR 0-6), 1 (0-1.9), and 0.5 days (single dose) in groups A, B, and C, respectively (p < 0.001). Median length of hospitalization was 4 days (2.5-7.5), 2 (1-3.7), and 0.5 (0.3-0.7), respectively (p < 0.001). Median hospitalization costs were $5458 (2676-6274) in group A, $2796 (2062-5726) in group B, and $921 (765-1230) in group C (p < 0.0001). Rapid EV detection in CSF by a fully-automated PCR improves management of AM by significantly reducing antibiotic use, hospitalization length and costs. Copyright © 2014 Elsevier B.V. All rights reserved.
Standards and guidelines applicable for the validation of programmable automation systems

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.

1993-02-01

The validation of programmable automation system for an application important to safety in a nuclear power plant requires a comprehensive view about the system quality and reliability. One central point is to get assured that proper international guidelines and standards have been followed in the design, construction and maintenance of the system. The study was directed to locate international standards and guidelines which can support the validation of programmable systems and to evaluate their applicability for the validation of systems on different levels of requirement during their life cycle. The publication reviews the most important international standards (IAEA, ISO, IEC, IEEE) and their basic principles both for system and application program. Several nuclear standards, which have drawn the main attention, and some general programmable automation standards have been examined. In addition one practical automation system has been examined in order to find essential questions. Based on these studies a set of important items for the qualification have been identified
Nuclear Energy Research Initiative Project No. 02 103 Innovative Low Cost Approaches to Automating QA/QC of Fuel Particle Production Using On Line Nondestructive Methods for Higher Reliability Final Project Report

Energy Technology Data Exchange (ETDEWEB)

Ahmed, Salahuddin; Batishko, Charles R.; Flake, Matthew; Good, Morris S.; Mathews, Royce; Morra, Marino; Panetta, Paul D.; Pardini, Allan F.; Sandness, Gerald A.; Tucker, Brian J.; Weier, Dennis R.; Hockey, Ronald L.; Gray, Joseph N.; Saurwein, John J.; Bond, Leonard J.; Lowden, Richard A.; Miller, James H.

2006-02-28

This Nuclear Energy Research Initiative (NERI) project was tasked with exploring, adapting, developing and demonstrating innovative nondestructive test methods to automate nuclear coated particle fuel inspection so as to provide the United States (US) with necessary improved and economical Quality Assurance and Control (QA/QC) that is needed for the fuels for several reactor concepts being proposed for both near term deployment [DOE NE & NERAC, 2001] and Generation IV nuclear systems. Replacing present day QA/QC methods, done manually and in many cases destructively, with higher speed automated nondestructive methods will make fuel production for advanced reactors economically feasible. For successful deployment of next generation reactors that employ particle fuels, or fuels in the form of pebbles based on particles, extremely large numbers of fuel particles will require inspection at throughput rates that do not significantly impact the proposed manufacturing processes. The focus of the project is nondestructive examination (NDE) technologies that can be automated for production speeds and make either: (I) On Process Measurements or (II) In Line Measurements. The inspection technologies selected will enable particle “quality” qualification as a particle or group of particles passes a sensor. A multiple attribute dependent signature will be measured and used for qualification or process control decisions. A primary task for achieving this objective is to establish standard signatures for both good/acceptable particles and the most problematic types of defects using several nondestructive methods.
Preface to the special section on human factors and automation in vehicles: designing highly automated vehicles with the driver in mind.

Science.gov (United States)

Merat, Natasha; Lee, John D

2012-10-01

This special section brings together diverse research regarding driver interaction with advanced automotive technology to guide design of increasingly automated vehicles. Rapidly evolving vehicle automation will likely change cars and trucks more in the next 5 years than the preceding 50, radically redefining what it means to drive. This special section includes 10 articles from European and North American researchers reporting simulator and naturalistic driving studies. Little research has considered the consequences of fully automated driving, with most focusing on lane-keeping and speed control systems individually. The studies reveal two underlying design philosophies: automate driving versus support driving. Results of several studies, consistent with previous research in other domains, suggest that the automate philosophy can delay driver responses to incidents in which the driver has to intervene and take control from the automation. Understanding how to orchestrate the transfer or sharing of control between the system and the driver, particularly in critical incidents, emerges as a central challenge. Designers should not assume that automation can substitute seamlessly for a human driver, nor can they assume that the driver can safely accommodate the limitations of automation. Designers, policy makers, and researchers must give careful consideration to what role the person should have in highly automated vehicles and how to support the driver if the driver is to be responsible for vehicle control. As in other domains, driving safety increasingly depends on the combined performance of the human and automation, and successful designs will depend on recognizing and supporting the new roles of the driver.
Alternative long term strategies for sustainable development: Rapidly increasing electricity consumption in Asian countries and future role of nuclear energy

International Nuclear Information System (INIS)

Sagawa, N.

1997-01-01

Many people in the world express the concern that global warming will become an increasingly serious problem. A rapid increase in population and demand for energy in the Asian region must be discussed in this context. Despite the forecast of an increase in demand for energy, the Asian region is short of oil and natural gas resources. In addition, only less energy can be supplied by renewable energy sources in the Asian region than in the other regions because of high population density. Nuclear energy is an important energy resource for fulfilling the future increasing energy demand in the Asian region and for contributing to the suppression of carbon dioxide emissions. In the Asian region alone, however, we cannot rely limitlessly on LWR which does not use plutonium. According to a scenario analysis, the total capacity of nuclear power plants in the Asian region would reach large scale and the cumulative amount of demand for natural uranium will increase to about 5 million tons in the Asian region alone. Just the nuclear power plants of this scale in Asia alone will rapidly consume the world's cheap natural uranium resources if we rely only on natural uranium. In the Asian region, few countries have embarked on nuclear power generation and the capacity of equipment is still small. Currently, however, many plans for nuclear power generation are being designed. Many Asian countries obviously consider nuclear power generation as a valid option. Many potential policies must be examined in the light of future uncertainty. In the future, both renewable energy and nuclear energy must be resorted to. When nuclear energy is utilized, the use of plutonium and FBR in the Asian region must be taken into account in order to attain continual growth and development. (author)
Automation of the dicentric chromosome assay and related assays

International Nuclear Information System (INIS)

Balajee, Adayabalam S.; Dainiak, Nicholas

2016-01-01

Dicentric Chromosome Assay (DCA) is considered to be the 'gold standard' for personalized dose assessment in humans after accidental or incidental radiation exposure. Although this technique is superior to other cytogenetic assays in terms of specificity and sensitivity, its potential application to radiation mass casualty scenarios is highly restricted because DCA is time consuming and labor intensive when performed manually. Therefore, it is imperative to develop high throughput automation techniques to make DCA suitable for radiological triage scenarios. At the Cytogenetic Biodosimetry Laboratory in Oak Ridge, efforts are underway to develop high throughput automation of DCA. Current status on development of various automated cytogenetic techniques in meeting the biodosimetry needs of radiological/nuclear incident(s) will be discussed
ASTROS: A multidisciplinary automated structural design tool

Science.gov (United States)

Neill, D. J.

1989-01-01

ASTROS (Automated Structural Optimization System) is a finite-element-based multidisciplinary structural optimization procedure developed under Air Force sponsorship to perform automated preliminary structural design. The design task is the determination of the structural sizes that provide an optimal structure while satisfying numerous constraints from many disciplines. In addition to its automated design features, ASTROS provides a general transient and frequency response capability, as well as a special feature to perform a transient analysis of a vehicle subjected to a nuclear blast. The motivation for the development of a single multidisciplinary design tool is that such a tool can provide improved structural designs in less time than is currently needed. The role of such a tool is even more apparent as modern materials come into widespread use. Balancing conflicting requirements for the structure's strength and stiffness while exploiting the benefits of material anisotropy is perhaps an impossible task without assistance from an automated design tool. Finally, the use of a single tool can bring the design task into better focus among design team members, thereby improving their insight into the overall task.
Proceedings of the 11. International symposium on the interaction of fast neutrons with nuclei - Automation of experiments in nuclear physics using mini- and microcomputers, organized by the Technical Univ. of Dresden, 30 Nov - 4 Dec 1981, Rathen, GDR

International Nuclear Information System (INIS)

Eckstein, P.; Meiling, W.

1982-07-01

The 11. International Symposium concentrated on automation of experiments in nuclear physics using mini- and microcomputers. The more than 30 contributions can be arranged into three groups: (i) hardware and software of computer-aided measuring devices and applications, (ii) automated measurements and methods of control, (iii) special problems of construction and control of neutron generators and accelerators
The development of application technology for image processing in nuclear facilities

International Nuclear Information System (INIS)

Lee, Jong Min; Lee, Yong Bum; Kim, Woog Ki; Sohn, Surg Won; Kim, Seung Ho; Hwang, Suk Yeoung; Kim, Byung Soo

1991-01-01

The object of this project is to develop application technology of image processing in nuclear facilities where image signal are used for reliability and safety enhancement of operation, radiation exposure reduce of operator, and automation of operation processing. We has studied such application technology for image processing in nuclear facilities as non-tactile measurement, remote and automatic inspection, remote control, and enhanced analysis of visual information. On these bases, automation system and real-time image processing system are developed. Nuclear power consists in over 50% share of electic power supply of our country nowdays. So, it is required of technological support for top-notch technology in nuclear industry and its related fields. Especially, it is indispensable for image processing technology to enhance the reliabilty and safety of operation, to automate the process in a place like a nuclear power plant and radioactive envionment. It is important that image processing technology is linked to a nuclear engineering, and enhance the reliability abd safety of nuclear operation, as well as decrease the dose rate. (Author)
Exposing exposure: enhancing patient safety through automated data mining of nuclear medicine reports for quality assurance and organ dose monitoring.

Science.gov (United States)

Ikuta, Ichiro; Sodickson, Aaron; Wasser, Elliot J; Warden, Graham I; Gerbaudo, Victor H; Khorasani, Ramin

2012-08-01

To develop and validate an open-source informatics toolkit capable of creating a radiation exposure data repository from existing nuclear medicine report archives and to demonstrate potential applications of such data for quality assurance and longitudinal patient-specific radiation dose monitoring. This study was institutional review board approved and HIPAA compliant. Informed consent was waived. An open-source toolkit designed to automate the extraction of data on radiopharmaceuticals and administered activities from nuclear medicine reports was developed. After iterative code training, manual validation was performed on 2359 nuclear medicine reports randomly selected from September 17, 1985, to February 28, 2011. Recall (sensitivity) and precision (positive predictive value) were calculated with 95% binomial confidence intervals. From the resultant institutional data repository, examples of usage in quality assurance efforts and patient-specific longitudinal radiation dose monitoring obtained by calculating organ doses from the administered activity and radiopharmaceutical of each examination were provided. Validation statistics yielded a combined recall of 97.6% ± 0.7 (95% confidence interval) and precision of 98.7% ± 0.5. Histograms of administered activity for fluorine 18 fluorodeoxyglucose and iodine 131 sodium iodide were generated. An organ dose heatmap which displays a sample patient's dose accumulation from multiple nuclear medicine examinations was created. Large-scale repositories of radiation exposure data can be extracted from institutional nuclear medicine report archives with high recall and precision. Such repositories enable new approaches in radiation exposure patient safety initiatives and patient-specific radiation dose monitoring.
Automated Structure Solution with the PHENIX Suite

Energy Technology Data Exchange (ETDEWEB)

Zwart, Peter H.; Zwart, Peter H.; Afonine, Pavel; Grosse-Kunstleve, Ralf W.; Hung, Li-Wei; Ioerger, Tom R.; McCoy, A.J.; McKee, Eric; Moriarty, Nigel; Read, Randy J.; Sacchettini, James C.; Sauter, Nicholas K.; Storoni, L.C.; Terwilliger, Tomas C.; Adams, Paul D.

2008-06-09

Significant time and effort are often required to solve and complete a macromolecular crystal structure. The development of automated computational methods for the analysis, solution and completion of crystallographic structures has the potential to produce minimally biased models in a short time without the need for manual intervention. The PHENIX software suite is a highly automated system for macromolecular structure determination that can rapidly arrive at an initial partial model of a structure without significant human intervention, given moderate resolution and good quality data. This achievement has been made possible by the development of new algorithms for structure determination, maximum-likelihood molecular replacement (PHASER), heavy-atom search (HySS), template and pattern-based automated model-building (RESOLVE, TEXTAL), automated macromolecular refinement (phenix.refine), and iterative model-building, density modification and refinement that can operate at moderate resolution (RESOLVE, AutoBuild). These algorithms are based on a highly integrated and comprehensive set of crystallographic libraries that have been built and made available to the community. The algorithms are tightly linked and made easily accessible to users through the PHENIX Wizards and the PHENIX GUI.
Automated structure solution with the PHENIX suite

Energy Technology Data Exchange (ETDEWEB)

Terwilliger, Thomas C [Los Alamos National Laboratory; Zwart, Peter H [LBNL; Afonine, Pavel V [LBNL; Grosse - Kunstleve, Ralf W [LBNL

2008-01-01

Significant time and effort are often required to solve and complete a macromolecular crystal structure. The development of automated computational methods for the analysis, solution, and completion of crystallographic structures has the potential to produce minimally biased models in a short time without the need for manual intervention. The PHENIX software suite is a highly automated system for macromolecular structure determination that can rapidly arrive at an initial partial model of a structure without significant human intervention, given moderate resolution, and good quality data. This achievement has been made possible by the development of new algorithms for structure determination, maximum-likelihood molecular replacement (PHASER), heavy-atom search (HySS), template- and pattern-based automated model-building (RESOLVE, TEXTAL), automated macromolecular refinement (phenix. refine), and iterative model-building, density modification and refinement that can operate at moderate resolution (RESOLVE, AutoBuild). These algorithms are based on a highly integrated and comprehensive set of crystallographic libraries that have been built and made available to the community. The algorithms are tightly linked and made easily accessible to users through the PHENIX Wizards and the PHENIX GUI.
Rapid DNA analysis for automated processing and interpretation of low DNA content samples.

Science.gov (United States)

Turingan, Rosemary S; Vasantgadkar, Sameer; Palombo, Luke; Hogan, Catherine; Jiang, Hua; Tan, Eugene; Selden, Richard F

2016-01-01

Short tandem repeat (STR) analysis of casework samples with low DNA content include those resulting from the transfer of epithelial cells from the skin to an object (e.g., cells on a water bottle, or brim of a cap), blood spatter stains, and small bone and tissue fragments. Low DNA content (LDC) samples are important in a wide range of settings, including disaster response teams to assist in victim identification and family reunification, military operations to identify friend or foe, criminal forensics to identify suspects and exonerate the innocent, and medical examiner and coroner offices to identify missing persons. Processing LDC samples requires experienced laboratory personnel, isolated workstations, and sophisticated equipment, requires transport time, and involves complex procedures. We present a rapid DNA analysis system designed specifically to generate STR profiles from LDC samples in field-forward settings by non-technical operators. By performing STR in the field, close to the site of collection, rapid DNA analysis has the potential to increase throughput and to provide actionable information in real time. A Low DNA Content BioChipSet (LDC BCS) was developed and manufactured by injection molding. It was designed to function in the fully integrated Accelerated Nuclear DNA Equipment (ANDE) instrument previously designed for analysis of buccal swab and other high DNA content samples (Investigative Genet. 4(1):1-15, 2013). The LDC BCS performs efficient DNA purification followed by microfluidic ultrafiltration of the purified DNA, maximizing the quantity of DNA available for subsequent amplification and electrophoretic separation and detection of amplified fragments. The system demonstrates accuracy, precision, resolution, signal strength, and peak height ratios appropriate for casework analysis. The LDC rapid DNA analysis system is effective for the generation of STR profiles from a wide range of sample types. The technology broadens the range of sample

Automation Hooks Architecture for Flexible Test Orchestration - Concept Development and Validation

Science.gov (United States)

Lansdowne, C. A.; Maclean, John R.; Winton, Chris; McCartney, Pat

2011-01-01

The Automation Hooks Architecture Trade Study for Flexible Test Orchestration sought a standardized data-driven alternative to conventional automated test programming interfaces. The study recommended composing the interface using multicast DNS (mDNS/SD) service discovery, Representational State Transfer (Restful) Web Services, and Automatic Test Markup Language (ATML). We describe additional efforts to rapidly mature the Automation Hooks Architecture candidate interface definition by validating it in a broad spectrum of applications. These activities have allowed us to further refine our concepts and provide observations directed toward objectives of economy, scalability, versatility, performance, severability, maintainability, scriptability and others.
Transactinide nuclear chemistry at JAERI

International Nuclear Information System (INIS)

Nagame, Y.; Haba, H.; Tsukada, K.

2002-01-01

Nuclear chemistry study of trans actinide elements in Japan is currently being in progress at JAERI (Japan Atomic Energy Research Institute). We have developed new experimental apparatuses: a beam-line safety system for the usage of the gas-jet coupled radioactive 248 Cm target chamber, a rotating wheel catcher apparatus for the measurement of α and spontaneous fission decay of the transactinides, MANON (Measurement system for Alpha particles and spontaneous fission events ON line), and an automated rapid chemical separation apparatus based on the high performance liquid chromatography, AIDA (Automated Ion exchange separation system coupled with the Detection apparatus for Alpha spectroscopy). The transactinide nuclei, 261 Rf and 262 Db, have been successfully produced via the reactions of 248 Cm( 18 O,5n) and 248 Cm( 19 F,5n), respectively, and the excitation functions for each reaction have been measured to evaluate the optimum irradiation condition for the production of these nuclei. The maximum cross sections in each reaction were 13 nb at the 18 O beam energy of 94-MeV and 1.5 Nb at the 103-MeV 19 F beam energy. On-line ion exchange experiments of Rf together with the lighter homologues Zr and Hf in the HCl, HNO 3 and HF solutions with AIDA have been carried out, and the results clearly show that the behavior of Rf is typical of the group-4 element. Relativistic molecular orbital calculations of the chloride and nitrate complexes of tetravalent Rf are also being performed to gain an understanding of the complex chemistry. Prospects and some recent experimental results for the nuclear chemistry study of the transactinide elements at JAERI are discussed. (author)
Super safe small reactor RAPID-L conceptual design and R and D. JAERI's nuclear research promotion program, H11-002 (Contract research)

International Nuclear Information System (INIS)

Kambe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Kawasaki, Akira; Iwamura, Takamichi

2003-03-01

The 200 kWe uranium nitride fueled lithium cooled fast reactor 'RAPID-L' combined with thermoelectric power conversion system that can be operated unmanned without refueling for up to ten years has been demonstrated. The RAPID refueling concept enables quick and simplified refueling, and achieves plant design lifetime over 20 years. A significant advantage of the RAPID-L design, which does not require the use of control rods - is the introduction of the innovative reactivity control systems: lithium expansion module (LEM), lithium injection module (LIM) and lithium release module (LRM). LEM is the most promising candidate for improving inherent reactivity feedback. LEMs could realize burnup compensation. LIMs assure sufficient negative reactivity feedback in unprotected transients. LRMs enable an automated reactor startup by detecting the hot standby temperature of the primary coolant. All these systems use 6 Li as liquid poison and are actuated by highly reliable physical properties (volume expansion of 6 Li for LEM, and freeze seal melting for LIM and LRM). (author)
Cold exposure rapidly induces virtual saturation of brown adipose tissue nuclear T3 receptors

International Nuclear Information System (INIS)

Bianco, A.C.; Silva, J.E.

1988-01-01

Cold exposure induces a rapid increase in uncoupling protein (UCP) concentration in the brown adipose tissue (BAT) of euthyroid, but not hypothyroid, rats. To normalize this response with exogenous 3,5,3'-triiodothyronine (T 3 ), it is necessary to cause systemic hyperthyroidism. In contrast, the same result can be obtained with just replacement doses of thyroxine (T 4 ) and, in euthyroid rats, the normal response of UCP to cold occurs without hyperthyroid plasma T 3 levels. Consequently, the authors explored the possibility that the cold-induced activation of the type II 5'-deiodinase resulted in high levels of nuclear T 3 receptor occupancy in euthyroid rats. Studies were performed with pulse injections of tracer T 3 or T 4 in rats exposed to 4 degree C for different lengths of time (1 h-3 wk). Within 4 h of cold exposure, they observed a significant increase in the nuclear [ 125 I]T 3 derived from the tracer [ 125 I]T 4 injections (T 3 [T 4 ]) and a significant reduction in the nuclear [ 125 I]T 3 derived from [ 125 I]T 3 injections (T 3 [T 3 ]). The number of BAT nuclear T 3 receptors did not increase for up to 3 wk of observation at 4 degree C. The mass of nuclear-bound T 3 was calculated from the nuclear tracer [ 125 I]T 3 [T 3 ] and [ 125 I]T 3 [T 4 ] at equilibrium and the specific activity of serum T 3 and T 4 , respectively. By 4 h after the initiation of the cold exposure, the receptors were >95% occupied and remained so for the 3 weeks of observation. They conclude that the simultaneous activation of the deiodinase with adrenergic BAT stimulation serves the purpose of nearly saturating the nuclear T 3 receptors. This makes possible the realization of the full thermogenic potential of the tissue without causing systemic hyperthyroidism
Automated procedure for performing computer security risk analysis

International Nuclear Information System (INIS)

Smith, S.T.; Lim, J.J.

1984-05-01

Computers, the invisible backbone of nuclear safeguards, monitor and control plant operations and support many materials accounting systems. Our automated procedure to assess computer security effectiveness differs from traditional risk analysis methods. The system is modeled as an interactive questionnaire, fully automated on a portable microcomputer. A set of modular event trees links the questionnaire to the risk assessment. Qualitative scores are obtained for target vulnerability, and qualitative impact measures are evaluated for a spectrum of threat-target pairs. These are then combined by a linguistic algebra to provide an accurate and meaningful risk measure. 12 references, 7 figures
Rapid, automated, nonradiometric susceptibility testing of Mycobacterium tuberculosis complex to four first-line antituberculous drugs used in standard short-course chemotherapy

DEFF Research Database (Denmark)

Johansen, Isik Somuncu; Thomsen, Vibeke Østergaard; Marjamäki, Merja

2004-01-01

The increasing prevalence of drug-resistant tuberculosis necessitates rapid and accurate susceptibility testing. The nonradiometric BACTEC Mycobacteria Growth Indicator Tube 960 (MGIT) system for susceptibility testing was evaluated on 222 clinical Mycobacterium tuberculosis complex isolates...... for isoniazid, rifampin, and ethambutol. Fifty-seven of the isolates were tested for pyrazinamide. Results were compared to those of radiometric BACTEC 460 system and discrepancies were resolved by the agar proportion method. We found an overall agreement of 99.0% for isoniazid, 99.5% for rifampin, 98.......2% for ethambutol, and 100% for pyrazinamide. After resolution of discrepancies, MGIT yielded no false susceptibility for rifampin and isoniazid. Although turnaround times were comparable, MGIT provides an advantage as inoculation can be done on any weekday as the growth is monitored automatically. The automated...
Automated Non-Destructive Testing Array Evaluation System

Energy Technology Data Exchange (ETDEWEB)

Wei, T.; Zavaljevski, N.; Bakhtiari, S.; Miron, A.; Jupperman, D.

2004-12-31

Utilities perform eddy current tests on nuclear power plant steam generator (SG) tubes to detect degradation. This report summarizes the status of ongoing research to develop signal processing algorithms that automate analysis of eddy current test data. The research focuses on analyzing array probe data for detecting, classifying, and characterizing degradation in SG tubes.
Automated Non-Destructive Testing Array Evaluation System

International Nuclear Information System (INIS)

Wei, T.; Zavaljevski, N.; Bakhtiari, S.; Miron, A.; Kupperman, D.

2004-01-01

Utilities perform eddy current tests on nuclear power plant steam generator (SG) tubes to detect degradation. This report summarizes the status of ongoing research to develop signal processing algorithms that automate analysis of eddy current test data. The research focuses on analyzing array probe data for detecting, classifying, and characterizing degradation in SG tubes
Automation of scanning technique by gamma radiation

International Nuclear Information System (INIS)

Aamira, Yahya

2011-01-01

The gamma scan technique is a nuclear test allowing the analysis of the internal mechanical properties of distillation columns used in petrochemical industries. Such technique is performed manually. So we propose in this work to automate the gamma scan procedure test by using a PLC. In addition, supervision and data acquisition interfaces are proposed.
Safety aspects of nuclear power plant automation and robotics

International Nuclear Information System (INIS)

1992-10-01

The question being considered in this report is the extent to which the following aims are promoted through the use of robotics and automatic plant systems: nuclear power is safe (nuclear power plants and related facilities will not be constructed or allowed to continue operating if they are not perceived as being safe); nuclear power is economic (in comparison to other forms of electricity production once the environmental costs have been fully considered and as part of a unified energy policy); nuclear power is conservative (using nuclear fuel does not waste natural resources, damage the atmosphere, or produce unmanageable waste). Refs, figs, tabs
New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities

Energy Technology Data Exchange (ETDEWEB)

Brim, Cornelia P.

2013-04-01

An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.
Automated ultrasonic scanning of flat plate nuclear fuel

International Nuclear Information System (INIS)

Barna, B.A.

1979-01-01

One of the most challenging problems in Non-Destructive Testing lies in making the inspection as rapid, precise, cost effective and operator independent as possible. Only by optimizing these four factors can a technology take full advantage of the quality control possible with NDT. This paper describes a highly complex application of high frequency ultrasonics to image extremely small and difficult to detect flaws in a production line environment. The objects of interest are flat plate nuclear fuel used in the Advanced Test Reactor at the Idaho National Engineering Laboratory. The plates are fabricated by hot rolling a sandwich of alloyed uranium fuel and aluminum cladding. After rolling, the block is flattened to a long thin plate approximately 1.27 m (55 inches) long, 102 mm (4 inches) wide and 1.25 mm (0.050 inches) thick. The core, or fuel area is nominally 0.75 mm (0.030 inches) thick with 0.25 mm (0.010 inches) of aluminum bonded to both sides. As might be expected the fabrication is a sensitive process which can introduce several flaws detrimental to the reactor operation if they are undetected. Two of the characteristics that must be examined are the cladding thickness of the aluminum left over the fuel and the quality of bond between the cladding and the fuel. If either the cladding is too thin or the bonding inadequate thermal and/or corrosive activity can crack the protective cladding
Automated ultrasonic inspection system for nuclear power stations

International Nuclear Information System (INIS)

Anon.

1976-01-01

The automated system of ultrasonic inspection which was used to conduct weld inspections of the complex primary system of the Borselle PWR station is described. It relies upon mechanically traversing purpose designed multi-crystal ultrasonic probes along the welds. A number of probes are switched sequentially to provide a continuous scan. A typical scan rate of 120 scan/sec is achieved by a multiplexer capable of switching transmitter and receiver individually. The system has wide applications in other industries. (U.K.)
Rapid actinide analysis method coupling liquid chromatography/ICP-MS and "9"0Sr gas proportional counter in post-accidental situation environmental samples

International Nuclear Information System (INIS)

Habibi, Azza

2015-01-01

The present study follows the Fukushima power plant accident and aimed to develop an analytical method to achieve, during an emergency situation, a rapid identification and quantification of alpha and beta emitters in environmental samples. The first step of this study allowed us to list the alpha and beta emitters which can be released in the environment in case of a nuclear accident. The second step aimed towards the development of a rapid analysis method to quantify 17 radionuclides of U, Th, Pu, Am, Np and Sr. The main objective was the automation of the radiochemical separation step and its coupling for the measurement. The separation is performed using columns containing extraction resins, namely TEVA, TRU and Sr. The measurement is performed using an ICP-MS (inductively coupled plasma mass spectrometry) and in some cases a gas proportional counter to quantify radiostrontium ("8"9Sr and "9"0Sr). Excellent figures of merit were obtained, off line, with water (tap, river and sea water) and solid matrices (soil and aerosol filters), after a micro-wave digestion or an alkaline fusion dissolution followed by a Ca_3(PO_4)_2 coprecipitation. The proposed analytical strategy showed yields between 70 % and 100 % and standard deviations between 5 % and 10 %. The newly developed separation method was then automated and coupled on-line to ICP-MS. The operating parameters were optimized using a design of experiments and the results were processed with Minitab. The optimized automated separation coupled on-line to the ICP-MS allows the rapid quantification, in 1.5 h per sample, of U, Th, Pu, Am, Np and Sr with detection limits gain as high as 20 times for artificial radionuclide. (author)
Automated accounting systems for nuclear materials

International Nuclear Information System (INIS)

Erkkila, B.

1994-01-01

History of the development of nuclear materials accounting systems in USA and their purposes are considered. Many present accounting systems are based on mainframe computers with multiple terminal access. Problems of future improvement accounting systems are discussed
Automated ultrasonic testing--capabilities, limitations and methods

International Nuclear Information System (INIS)

Beller, L.S.; Mikesell, C.R.

1977-01-01

The requirements for precision and reproducibility of ultrasonic testing during inservice inspection of nuclear reactors are both quantitatively and qualitatively more severe than most current practice in the field can provide. An automated ultrasonic testing (AUT) system, which provides a significant advancement in field examination capabilities, is described. Properties of the system, its application, and typical results are discussed
Development of a web-based CANDU core management procedures automation system

International Nuclear Information System (INIS)

Lee, S.; Park, D.; Yeom, C.; Suh, H.

2007-01-01

Introduce CANDU core management procedures automation system (COMPAS) - A web-based application which semi-automates several CANDU core management tasks. It provides various functionalities including selection and evaluation of refueling channel, detector calibration, coolant flow estimation and thermal power calculation through automated interfacing with analysis codes (RFSP, NUCIRC, etc.) and plant data. It also utilizes brand new .NET computing technology such as ASP.NET, smart client, web services and so on. Since almost all functions are abstracted from the previous experiences of the current working members of the Wolsong Nuclear Power Plant (NPP), it will lead to an efficient and safe operation of CANDU plants. (author)
Development of a web-based CANDU core management procedures automation system

Energy Technology Data Exchange (ETDEWEB)

Lee, S.; Park, D.; Yeom, C. [Inst. for Advanced Engineering (IAE), Yongin (Korea, Republic of); Suh, H. [Korea Hydro and Nuclear Power (KHNP), Wolsong (Korea, Republic of)

2007-07-01

Introduce CANDU core management procedures automation system (COMPAS) - A web-based application which semi-automates several CANDU core management tasks. It provides various functionalities including selection and evaluation of refueling channel, detector calibration, coolant flow estimation and thermal power calculation through automated interfacing with analysis codes (RFSP, NUCIRC, etc.) and plant data. It also utilizes brand new .NET computing technology such as ASP.NET, smart client, web services and so on. Since almost all functions are abstracted from the previous experiences of the current working members of the Wolsong Nuclear Power Plant (NPP), it will lead to an efficient and safe operation of CANDU plants. (author)
Fossil power plant automation

International Nuclear Information System (INIS)

Divakaruni, S.M.; Touchton, G.

1991-01-01

This paper elaborates on issues facing the utilities industry and seeks to address how new computer-based control and automation technologies resulting from recent microprocessor evolution, can improve fossil plant operations and maintenance. This in turn can assist utilities to emerge stronger from the challenges ahead. Many presentations at the first ISA/EPRI co-sponsored conference are targeted towards improving the use of computer and control systems in the fossil and nuclear power plants and we believe this to be the right forum to share our ideas
A model for automation of radioactive dose control

International Nuclear Information System (INIS)

Ribeiro, Carlos Henrique Calazans; Zambon, Jose Waldir; Bitelli, Ricardo; Honaiser, Eduardo Henrique Rangel

2009-01-01

The paper presents a proposal for automation of the personnel dose control system to be used in nuclear medicine environments. The model has considered the Standards and rules of the National Commission of Nuclear Energy (CNEN) and of the Health Ministry. The advantages of the model is a robust management of the integrated dose and technicians qualification status. The software platform selected to be used was the Lotus Notes and an analysis of the advantages, disadvantages of the use of this platform is also presented. (author)

A model for automation of radioactive dose control

Energy Technology Data Exchange (ETDEWEB)

Ribeiro, Carlos Henrique Calazans; Zambon, Jose Waldir; Bitelli, Ricardo; Honaiser, Eduardo Henrique Rangel [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil)], e-mail: calazans@ctmsp.mar.mil.br, e-mail: zambon@ctmsp.mar.mil.br, e-mail: bitelli@ctmsp.mar.mil.br, e-mail: honaiser@ctmsp.mar.mil.br

2009-07-01

The paper presents a proposal for automation of the personnel dose control system to be used in nuclear medicine environments. The model has considered the Standards and rules of the National Commission of Nuclear Energy (CNEN) and of the Health Ministry. The advantages of the model is a robust management of the integrated dose and technicians qualification status. The software platform selected to be used was the Lotus Notes and an analysis of the advantages, disadvantages of the use of this platform is also presented. (author)
AUTOMATED TECHNIQUE FOR FLOW MEASUREMENTS FROM MARIOTTE RESERVOIRS.

Science.gov (United States)

Constantz, Jim; Murphy, Fred

1987-01-01

The mariotte reservoir supplies water at a constant hydraulic pressure by self-regulation of its internal gas pressure. Automated outflow measurements from mariotte reservoirs are generally difficult because of the reservoir's self-regulation mechanism. This paper describes an automated flow meter specifically designed for use with mariotte reservoirs. The flow meter monitors changes in the mariotte reservoir's gas pressure during outflow to determine changes in the reservoir's water level. The flow measurement is performed by attaching a pressure transducer to the top of a mariotte reservoir and monitoring gas pressure changes during outflow with a programmable data logger. The advantages of the new automated flow measurement techniques include: (i) the ability to rapidly record a large range of fluxes without restricting outflow, and (ii) the ability to accurately average the pulsing flow, which commonly occurs during outflow from the mariotte reservoir.
Classroom Evaluation of a Rapid Prototyping System.

Science.gov (United States)

Tennyson, Stephen A.; Krueger, Thomas J.

2001-01-01

Introduces rapid prototyping which creates virtual models through a variety of automated material additive processes. Relates experiences using JP System 5 in freshman and sophomore engineering design graphics courses. Analyzes strengths and limitations of the JP System 5 and discusses how to use it effectively. (Contains 15 references.)…
Development of automated controller system for controlling reactivity by using FPGA in research reactor application

International Nuclear Information System (INIS)

Mohd Sabri Minhat; Izhar Abu Hussin; Mohd Idris Taib

2012-01-01

The scope for this research paper is to produce a detail design for Development of Automated Controller System for Controlling Reactivity by using FPGA in Research Reactor Application for high safety nuclear operation. The development of this project including design, purchasing, fabrication, installation, testing and validation and verification for one prototype automated controller system for controlling reactivity in industry local technology for human capacity and capability development towards the first Nuclear Power Programme (NPP) in Malaysia. The specific objectives of this research paper are to Development of Automated Controller System for Controlling Reactivity (ACSCR) in Research Reactor Application (PUSPATI TRIGA Reactor) by using simultaneous movement method; To design, fabricate and produce the accuracy of Control Rods Drive Mechanism to 0.1 mm resolution using a stepper motor as an actuator; To design, install and produce the system response to be more faster by using Field Programmable Gate Array (FPGA) and High Speed Computer; and to improve the Safety Level of the Research Reactor in high safety nuclear operation condition. (author)
Trust in automation and meta-cognitive accuracy in NPP operating crews

Energy Technology Data Exchange (ETDEWEB)

Skraaning Jr, G.; Miberg Skjerve, A. B. [OECD Halden Reactor Project, PO Box 173, 1751 Halden (Norway)

2006-07-01

Nuclear power plant operators can over-trust or under-trust automation. Operator trust in automation is said to be mis-calibrated when the level of trust is not corresponding to the actual level of automation reliability. A possible consequence of mis-calibrated trust is degraded meta-cognitive accuracy. Meta-cognitive accuracy is the ability to correctly monitor the effectiveness of ones own performance while engaged in complex tasks. When operators misjudge their own performance, human control actions will be poorly regulated and safety and/or efficiency may suffer. An analysis of simulator data showed that meta-cognitive accuracy and trust in automation were highly correlated for knowledge-based scenarios, but uncorrelated for rule-based scenarios. In the knowledge-based scenarios, the operators overestimated their performance effectiveness under high levels of trust, they underestimated performance under low levels of trust, but showed realistic self-assessment under intermediate levels of trust in automation. The result was interpreted to suggest that trust in automation impact the meta-cognitive accuracy of the operators. (authors)
Trust in automation and meta-cognitive accuracy in NPP operating crews

International Nuclear Information System (INIS)

Skraaning Jr, G.; Miberg Skjerve, A. B.

2006-01-01

Nuclear power plant operators can over-trust or under-trust automation. Operator trust in automation is said to be mis-calibrated when the level of trust is not corresponding to the actual level of automation reliability. A possible consequence of mis-calibrated trust is degraded meta-cognitive accuracy. Meta-cognitive accuracy is the ability to correctly monitor the effectiveness of ones own performance while engaged in complex tasks. When operators misjudge their own performance, human control actions will be poorly regulated and safety and/or efficiency may suffer. An analysis of simulator data showed that meta-cognitive accuracy and trust in automation were highly correlated for knowledge-based scenarios, but uncorrelated for rule-based scenarios. In the knowledge-based scenarios, the operators overestimated their performance effectiveness under high levels of trust, they underestimated performance under low levels of trust, but showed realistic self-assessment under intermediate levels of trust in automation. The result was interpreted to suggest that trust in automation impact the meta-cognitive accuracy of the operators. (authors)
Nuclear power plant personnel qualifications and training: TAPS: the task analysis profiling system. Volume 2

International Nuclear Information System (INIS)

Jorgensen, C.C.

1985-06-01

This report discusses an automated task analysis profiling system (TAPS) designed to provide a linking tool between the behaviors of nuclear power plant operators in performing their tasks and the measurement tools necessary to evaluate their in-plant performance. TAPS assists in the identification of the entry-level skill, knowledge, ability and attitude (SKAA) requirements for the various tasks and rapidly associates them with measurement tests and human factors principles. This report describes the development of TAPS and presents its first demonstration. It begins with characteristics of skilled human performance and proceeds to postulate a cognitive model to formally describe these characteristics. A method is derived for linking SKAA characteristics to measurement tests. The entire process is then automated in the form of a task analysis computer program. The development of the program is detailed and a user guide with annotated code listings and supporting test information is provided
A semi-automated method for rapid detection of ripple events on interictal voltage discharges in the scalp electroencephalogram.

Science.gov (United States)

Chu, Catherine J; Chan, Arthur; Song, Dan; Staley, Kevin J; Stufflebeam, Steven M; Kramer, Mark A

2017-02-01

High frequency oscillations are emerging as a clinically important indicator of epileptic networks. However, manual detection of these high frequency oscillations is difficult, time consuming, and subjective, especially in the scalp EEG, thus hindering further clinical exploration and application. Semi-automated detection methods augment manual detection by reducing inspection to a subset of time intervals. We propose a new method to detect high frequency oscillations that co-occur with interictal epileptiform discharges. The new method proceeds in two steps. The first step identifies candidate time intervals during which high frequency activity is increased. The second step computes a set of seven features for each candidate interval. These features require that the candidate event contain a high frequency oscillation approximately sinusoidal in shape, with at least three cycles, that co-occurs with a large amplitude discharge. Candidate events that satisfy these features are stored for validation through visual analysis. We evaluate the detector performance in simulation and on ten examples of scalp EEG data, and show that the proposed method successfully detects spike-ripple events, with high positive predictive value, low false positive rate, and high intra-rater reliability. The proposed method is less sensitive than the existing method of visual inspection, but much faster and much more reliable. Accurate and rapid detection of high frequency activity increases the clinical viability of this rhythmic biomarker of epilepsy. The proposed spike-ripple detector rapidly identifies candidate spike-ripple events, thus making clinical analysis of prolonged, multielectrode scalp EEG recordings tractable. Copyright © 2016 Elsevier B.V. All rights reserved.
Is rapid development of nuclear power purposeful

Energy Technology Data Exchange (ETDEWEB)

1977-01-01

The questions of the development of nuclear energy are discussed with regard to the efficacy of investments. The results are given of studies carried out at the nuclear research institute in Juelich in the FRG. At the estimated 25 years' service-life of the reactor and 0.2% uranium concentration in ore the following results were obtained: Total energy consumption for the construction and operation of a light water reactor power plant makes up 4.6% of the total power production, and in high-temperature reactors it amounts to 3.5%, both with uranium enrichment by the diffusion process. In uranium enrichment by centrifugal technology, consumption drops to 1.25% for LWRms and to 0.9% for high-temperature reactors, in fast breeder reactors it makes up only 0.8% of the total power production of the nuclear power plant. The period during which a nuclear power plant produces the amount of power consumed in construction and operation is 1.2 to 2.5 months which makes it less costly and more economical than any power plant burning coal minus the negative environmental impacts of such power plants.
Summarizing documentation of the laboratory automation system RADAR for the analytical services of a nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Brandenburg, G.; Brocke, W.; Brodda, B.G.; Buerger, K.; Halling, H.; Heer, H.; Puetz, K.; Schaedlich, W.; Watzlawik, K.H.

1981-12-01

The essential tasks of the system are on-line open-loop process control based on in-line measurements and automation of the off-line analytical laboratory. The in-line measurements (at 55 tanks of the chemical process area) provide density-, liquid-, level-, and temperature values. The concentration value of a single component may easily be determined, if the solution consists of no more than two phases. The automation of the off-line analytical laboratory contains laboratory organization including sample management and data organization and computer-aided sample transportation control, data acquisition and data processing at chemical and nuclear analytical devices. The computer system consists of two computer-subsystems: a front end system for sample central registration and in-line process control and a central size system for the off-line analytical tasks. The organization of the application oriented system uses a centralized data base. Similar data processing functions concerning different analytical management tasks are structured into the following subsystem: man machine interface, interrupt- and data acquisition system, data base, protocol service and data processing. The procedures for the laboratory management (organization and experiment sequences) are defined by application data bases. Following the project phases, engineering requirements-, design-, assembly-, start up- and test run phase are described. In addition figures on expenditure and experiences are given and the system concept is discussed. (orig./HP) [de
Performance of the new automated Abbott RealTime MTB assay for rapid detection of Mycobacterium tuberculosis complex in respiratory specimens.

Science.gov (United States)

Chen, J H K; She, K K K; Kwong, T-C; Wong, O-Y; Siu, G K H; Leung, C-C; Chang, K-C; Tam, C-M; Ho, P-L; Cheng, V C C; Yuen, K-Y; Yam, W-C

2015-09-01

The automated high-throughput Abbott RealTime MTB real-time PCR assay has been recently launched for Mycobacterium tuberculosis complex (MTBC) clinical diagnosis. This study would like to evaluate its performance. We first compared its diagnostic performance with the Roche Cobas TaqMan MTB assay on 214 clinical respiratory specimens. Prospective analysis of a total 520 specimens was then performed to further evaluate the Abbott assay. The Abbott assay showed a lower limit of detection at 22.5 AFB/ml, which was more sensitive than the Cobas assay (167.5 AFB/ml). The two assays demonstrated a significant difference in diagnostic performance (McNemar's test; P = 0.0034), in which the Abbott assay presented significantly higher area under curve (AUC) than the Cobas assay (1.000 vs 0.880; P = 0.0002). The Abbott assay demonstrated extremely low PCR inhibition on clinical respiratory specimens. The automated Abbott assay required only very short manual handling time (0.5 h), which could help to improve the laboratory management. In the prospective analysis, the overall estimates for sensitivity and specificity of the Abbott assay were both 100 % among smear-positive specimens, whereas the smear-negative specimens were 96.7 and 96.1 %, respectively. No cross-reactivity with non-tuberculosis mycobacterial species was observed. The superiority in sensitivity of the Abbott assay for detecting MTBC in smear-negative specimens could further minimize the risk in MTBC false-negative detection. The new Abbott RealTime MTB assay has good diagnostic performance which can be a useful diagnostic tool for rapid MTBC detection in clinical laboratories.
State of the art on construction automation and robotic system in domestic and foreign construction industry

International Nuclear Information System (INIS)

Lee, Sung Uk; Seo, Yong Chil; Jung, Seung Ho; Cho, Jai Wan; Choi, Young Soo

2007-08-01

In this report, we review the existing concept of construction automation and also survey the state of the art on construction automation and robotic system in domestic and foreign construction industry. On the basis of the result of review and survey, we want to suggest an applicable robotic technology to construction industry and points to be duly considered for activating construction automation. We investigate the state of the art on construction automation and robotic system in domestic and foreign construction industry and also applicable area and direction of domestic construction automation and robotic system. We hope that construction automation and robotic technology, which are improved rapidly nowadays, can contribute to the growth of construction industry
Automation of the helium jet transport system for nuclear recoil products; Automacao do sistema de transporte de nucleos de recuo por jato de helio

Energy Technology Data Exchange (ETDEWEB)

Bellido, Luis F.; Pedrosa, Paulo S

1996-09-01

A computer code and an interface hardware to automate the acquisition data and the sample changer in a helium jet transport system of recoil nucleus was developed for an IBM or compatible personal microcomputer. The software works with a Spectrum-ACE/ADCAM ORTEC`s multichannel analysers and the interface card uses the 03EFh port to command the sample changer. This system allows to measure, by gamma spectrometry, radionuclides with half-lives of order of seconds produced from nuclear reactions. (author) 3 refs.
A project in support of nuclear technology cooperation

International Nuclear Information System (INIS)

Hwang, Deok Ku; Choi, Pyung Hoon; Lee, Ji Ho

2001-12-01

The results and contents of the project are as follows; Establish strategies of international cooperation in an effort to promote our nation's leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB nd INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing
Bar code usage in nuclear materials accountability

International Nuclear Information System (INIS)

Mee, W.T.

1983-01-01

The age old method of physically taking an inventory of materials by listing each item's identification number has lived beyond its usefulness. In this age of computerization, which offers the local grocery store a quick, sure, and easy means to inventory, it is time for nuclear materials facilities to automate accountability activities. The Oak Ridge Y-12 Plant began investigating the use of automated data collection devices in 1979. At that time, bar code and optical-character-recognition (OCR) systems were reviewed with the purpose of directly entering data into DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). Both of these systems appeared applicable; however, other automated devices already employed for production control made implementing the bar code and OCR seem improbable. However, the DYMCAS was placed on line for nuclear material accountability, a decision was made to consider the bar code for physical inventory listings. For the past several months a development program has been underway to use a bar code device to collect and input data to the DYMCAS on the uranium recovery operations. Programs have been completed and tested, and are being employed to ensure that data will be compatible and useful. Bar code implementation and expansion of its use for all nuclear material inventory activity in Y-12 is presented
Computer-based accountability system (Phase I) for special nuclear materials at Argonne-West

International Nuclear Information System (INIS)

Ingermanson, R.S.; Proctor, A.E.

1982-05-01

An automated accountability system for special nuclear materials (SNM) is under development at Argonne National Laboratory-West. Phase I of the development effort has established the following basic features of the system: a unique file organization allows rapid updating or retrieval of the status of various SNM, based on batch numbers, storage location, serial number, or other attributes. Access to the program is controlled by an interactive user interface that can be easily understood by operators who have had no prior background in electronic data processing. Extensive use of structured programming techniques make the software package easy to understand and to modify for specific applications. All routines are written in FORTRAN
Flexible automation and manufacturing technology

International Nuclear Information System (INIS)

Ramakumar, M.S.

1994-01-01

Sponsored projects on mobile tele robots, machine vision systems, sensors, pick and place robots for micro electronics, prosthetic devices, surgeons aids, robots for welding and other industrial applications etc. are under development in India. The very significant capabilities in these areas available in our R and D agencies have been inducted into development work in robotics and automation. This is bound to provide an environment and thrust that will result in rapid significant progress. (author). 2 figs
Diversity requirements for safety critical software-based automation systems

International Nuclear Information System (INIS)

Korhonen, J.; Pulkkinen, U.; Haapanen, P.

1998-03-01

System vendors nowadays propose software-based systems even for the most critical safety functions in nuclear power plants. Due to the nature and mechanisms of influence of software faults new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)' various safety assessment methods and tools for software based systems are developed and evaluated. This report first discusses the (common cause) failure mechanisms in software-based systems, then defines fault-tolerant system architectures to avoid common cause failures, then studies the various alternatives to apply diversity and their influence on system reliability. Finally, a method for the assessment of diversity is described. Other recently published reports in OHA-report series handles the statistical reliability assessment of software based (STUK-YTO-TR 119), usage models in reliability assessment of software-based systems (STUK-YTO-TR 128) and handling of programmable automation in plant PSA-studies (STUK-YTO-TR 129)
Rapid-L Operator-Free Fast Reactor Concept Without Any Control Rods

International Nuclear Information System (INIS)

Kambe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Iwamura, Takamichi

2003-01-01

The 200-kW(electric) uranium-nitride-fueled lithium-cooled fast reactor concept 'RAPID-L' to achieve highly automated reactor operation has been demonstrated. RAPID-L is designed for a lunar base power system. It is one of the variants of the RAPID (Refueling by All Pins Integrated Design) fast reactor concept, which enables quick and simplified refueling. The essential feature of the RAPID concept is that the reactor core consists of an integrated fuel assembly instead of conventional fuel subassemblies. In this small-size reactor core, 2700 fuel pins are integrated and encased in a fuel cartridge. Refueling is conducted by replacing a fuel cartridge. The reactor can be operated without refueling for up to 10 yr.Unique challenges in reactivity control systems design have been addressed in the RAPID-L concept. The reactor has no control rod but involves the following innovative reactivity control systems: lithium expansion modules (LEM) for inherent reactivity feedback, lithium injection modules (LIM) for inherent ultimate shutdown, and lithium release modules (LRM) for automated reactor startup. All these systems adopt 6 Li as a liquid poison instead of B 4 C rods. In combination with LEMs, LIMs, and LRMs, RAPID-L can be operated without an operator. This reactor concept is also applicable to the terrestrial fast reactors. In this paper, the RAPID-L reactor concept and its transient characteristics are presented
Toward automated interpretation of integrated information: Managing "big data" for NDE

Science.gov (United States)

Gregory, Elizabeth; Lesthaeghe, Tyler; Holland, Stephen

2015-03-01

Large scale automation of NDE processes is rapidly maturing, thanks to recent improvements in robotics and the rapid growth of computer power over the last twenty years. It is fairly straightforward to automate NDE data collection itself, but the process of NDE remains largely manual. We will discuss three threads of technological needs that must be addressed before we are able to perform automated NDE. Spatial context, the first thread, means that each NDE measurement taken is accompanied by metadata that locates the measurement with respect to the 3D physical geometry of the specimen. In this way, the geometry of the specimen acts as a database key. Data context, the second thread, means that we record why the data was taken and how it was measured in addition to the NDE data itself. We will present our software tool that helps users interact with data in context, Databrowse. Condition estimation, the third thread, is maintaining the best possible knowledge of the condition (serviceability, degradation, etc.) of an object or part. In the NDE context, we can prospectively use Bayes' Theorem to integrate the data from each new NDE measurement with prior knowledge. These tools, combined with robotic measurements and automated defect analysis, will provide the information needed to make high-level life predictions and focus NDE measurements where they are needed most.

LAVA: Large scale Automated Vulnerability Addition

Science.gov (United States)

2016-05-23

LAVA: Large-scale Automated Vulnerability Addition Brendan Dolan -Gavitt∗, Patrick Hulin†, Tim Leek†, Fredrich Ulrich†, Ryan Whelan† (Authors listed...released, and thus rapidly become stale. We can expect tools to have been trained to detect bugs that have been released. Given the commercial price tag...low TCN) and dead (low liveness) program data is a powerful one for vulnera- bility injection. The DUAs it identifies are internal program quantities
Design automation of switching mode high voltage power supply for nuclear instruments

International Nuclear Information System (INIS)

El-araby, S.M.S.

1999-01-01

This paper presents an automation procedure for the design of switching mode high voltage power supplies, using Pc programming facility. The procedure permits the selection of a ready made or designed ferrite transformer. This selection could be achieved according to the designer desire; as the program includes complete information about ready made ferrite transformer through complete database. The procedure is based on suggested template circuit. Micro-Cap IV simulation package is used to verify the desired high voltage power supply design. Simulation results agree quite well with suggested procedure's results. Design aspects and development needed to increase automation capabilities are also discussed
Informational system to assist decision making at spent nuclear fuel transportation from VVER-440, VVER-1000 and RBMK-1000 nuclear power plants

International Nuclear Information System (INIS)

Kuryndin, A.V.; Kirkin, A.M.; Stroganov, A.A.

2012-01-01

The developed informational system provides an automated estimations of nuclear and radiation safety parameters during spent nuclear fuel transportation from WWER-440 and WWER-1000 and RBMK-1000 nuclear power plants to the nuclear fuel cycle facilities, and allows us to determine the optimum cask loading from the dose rates distribution outside of protection point of view [ru
Development of high performance liquid chromatography for rapid determination of burn-up of nuclear fuels

International Nuclear Information System (INIS)

Joseph, M.; Karunasagar, D.; Saha, B.

1996-01-01

Burn-up an important parameter during evaluation of the performance of any nuclear fuel. Among the various techniques available, the preferred one for its determination is based on accurate measurement of a suitable fission product monitor and the residual heavy elements. Since isotopes of rare earth elements are generally used as burn-up monitors, conditions were standardized for rapid separation (within 15 minutes) of light rare earths using high performance liquid chromatography based on either anion exchange (Partisil 10 SAX) in methanol-nitric acid medium or by cation exchange on a reverse phase column (Spherisorb 5-ODS-2 or Supelcosil LC-18) dynamically modified with 1-octane sulfonate or camphor-10-sulfonic acid (β). Both these methods were assessed for separation of individual fission product rare earths from their mixtures. A new approach has been examined in detail for rapid assay of neodymium, which appears promising for faster and accurate measurement of burn-up. (author)
Automated reasoning in man-machine control systems

International Nuclear Information System (INIS)

Stratton, R.C.; Lusk, E.L.

1983-01-01

This paper describes a project being undertaken at Argonne National Laboratory to demonstrate the usefulness of automated reasoning techniques in the implementation of a man-machine control system being designed at the EBR-II nuclear power plant. It is shown how automated reasoning influences the choice of optimal roles for both man and machine in the system control process, both for normal and off-normal operation. In addition, the requirements imposed by such a system for a rigorously formal specification of operating states, subsystem states, and transition procedures have a useful impact on the analysis phase. The definitions and rules are discussed for a prototype system which is physically simple yet illustrates some of the complexities inherent in real systems
Prompt and non-prompt J/$\\psi$ production and nuclear modification at mid-rapidity in p-Pb collisions at $\\sqrt{s_{\\rm NN}} = 5.02$ TeV

CERN Document Server

Acharya, Shreyasi; The ALICE collaboration; Adamova, Dagmar; Adolfsson, Jonatan; Aggarwal, Madan Mohan; Aglieri Rinella, Gianluca; Agnello, Michelangelo; Agrawal, Neelima; Ahammed, Zubayer; Ahn, Sang Un; Aiola, Salvatore; Akindinov, Alexander; Al-turany, Mohammad; Alam, Sk Noor; Silva De Albuquerque, Danilo; Aleksandrov, Dmitry; Alessandro, Bruno; Alfaro Molina, Jose Ruben; Ali, Yasir; Alici, Andrea; Alkin, Anton; Alme, Johan; Alt, Torsten; Altenkamper, Lucas; Altsybeev, Igor; Andrei, Cristian; Andreou, Dimitra; Andrews, Harry Arthur; Andronic, Anton; Angeletti, Massimo; Anguelov, Venelin; Anson, Christopher Daniel; Anticic, Tome; Antinori, Federico; Antonioli, Pietro; Apadula, Nicole; Aphecetche, Laurent Bernard; Appelshaeuser, Harald; Arcelli, Silvia; Arnaldi, Roberta; Arnold, Oliver Werner; Arsene, Ionut Cristian; Arslandok, Mesut; Audurier, Benjamin; Augustinus, Andre; Averbeck, Ralf Peter; Azmi, Mohd Danish; Badala, Angela; Baek, Yong Wook; Bagnasco, Stefano; Bailhache, Raphaelle Marie; Bala, Renu; Baldisseri, Alberto; Ball, Markus; Baral, Rama Chandra; Barbano, Anastasia Maria; Barbera, Roberto; Barile, Francesco; Barioglio, Luca; Barnafoldi, Gergely Gabor; Barnby, Lee Stuart; Ramillien Barret, Valerie; Bartalini, Paolo; Barth, Klaus; Bartsch, Esther; Bastid, Nicole; Basu, Sumit; Batigne, Guillaume; Batyunya, Boris; Batzing, Paul Christoph; Bazo Alba, Jose Luis; Bearden, Ian Gardner; Beck, Hans; Bedda, Cristina; Behera, Nirbhay Kumar; Belikov, Iouri; Bellini, Francesca; Bello Martinez, Hector; Bellwied, Rene; Espinoza Beltran, Lucina Gabriela; Belyaev, Vladimir; Bencedi, Gyula; Beole, Stefania; Bercuci, Alexandru; Berdnikov, Yaroslav; Berenyi, Daniel; Bertens, Redmer Alexander; Berzano, Dario; Betev, Latchezar; Bhaduri, Partha Pratim; Bhasin, Anju; Bhat, Inayat Rasool; Bhattacharjee, Buddhadeb; Bhom, Jihyun; Bianchi, Antonio; Bianchi, Livio; Bianchi, Nicola; Bielcik, Jaroslav; Bielcikova, Jana; Bilandzic, Ante; Biro, Gabor; Biswas, Rathijit; Biswas, Saikat; Blair, Justin Thomas; Blau, Dmitry; Blume, Christoph; Boca, Gianluigi; Bock, Friederike; Bogdanov, Alexey; Boldizsar, Laszlo; Bombara, Marek; Bonomi, Germano; Bonora, Matthias; Borel, Herve; Borissov, Alexander; Borri, Marcello; Botta, Elena; Bourjau, Christian; Bratrud, Lars; Braun-munzinger, Peter; Bregant, Marco; Broker, Theo Alexander; Broz, Michal; Brucken, Erik Jens; Bruna, Elena; Bruno, Giuseppe Eugenio; Budnikov, Dmitry; Buesching, Henner; Bufalino, Stefania; Buhler, Paul; Buncic, Predrag; Busch, Oliver; Buthelezi, Edith Zinhle; Bashir Butt, Jamila; Buxton, Jesse Thomas; Cabala, Jan; Caffarri, Davide; Caines, Helen Louise; Caliva, Alberto; Calvo Villar, Ernesto; Soto Camacho, Rabi; Camerini, Paolo; Capon, Aaron Allan; Carena, Francesco; Carena, Wisla; Carnesecchi, Francesca; Castillo Castellanos, Javier Ernesto; Castro, Andrew John; Casula, Ester Anna Rita; Ceballos Sanchez, Cesar; Chandra, Sinjini; Chang, Beomsu; Chang, Wan; Chapeland, Sylvain; Chartier, Marielle; Chattopadhyay, Subhasis; Chattopadhyay, Sukalyan; Chauvin, Alex; Cheshkov, Cvetan Valeriev; Cheynis, Brigitte; Chibante Barroso, Vasco Miguel; Dobrigkeit Chinellato, David; Cho, Soyeon; Chochula, Peter; Choudhury, Subikash; Chowdhury, Tasnuva; Christakoglou, Panagiotis; Christensen, Christian Holm; Christiansen, Peter; Chujo, Tatsuya; Chung, Suh-urk; Cicalo, Corrado; Cifarelli, Luisa; Cindolo, Federico; Cleymans, Jean Willy Andre; Colamaria, Fabio Filippo; Colella, Domenico; Collu, Alberto; Colocci, Manuel; Concas, Matteo; Conesa Balbastre, Gustavo; Conesa Del Valle, Zaida; Contreras Nuno, Jesus Guillermo; Cormier, Thomas Michael; Corrales Morales, Yasser; Cortes Maldonado, Ismael; Cortese, Pietro; Cosentino, Mauro Rogerio; Costa, Filippo; Costanza, Susanna; Crkovska, Jana; Crochet, Philippe; Cuautle Flores, Eleazar; Cunqueiro Mendez, Leticia; Dahms, Torsten; Dainese, Andrea; Danisch, Meike Charlotte; Danu, Andrea; Das, Debasish; Das, Indranil; Das, Supriya; Dash, Ajay Kumar; Dash, Sadhana; De, Sudipan; De Caro, Annalisa; De Cataldo, Giacinto; De Conti, Camila; De Cuveland, Jan; De Falco, Alessandro; De Gruttola, Daniele; De Marco, Nora; De Pasquale, Salvatore; Derradi De Souza, Rafael; Franz Degenhardt, Hermann; Deisting, Alexander; Deloff, Andrzej; Delsanto, Silvia; Deplano, Caterina; Dhankher, Preeti; Di Bari, Domenico; Di Mauro, Antonio; Di Ruzza, Benedetto; Arteche Diaz, Raul; Dietel, Thomas; Dillenseger, Pascal; Ding, Yanchun; Divia, Roberto; Djuvsland, Oeystein; Dobrin, Alexandru Florin; Domenicis Gimenez, Diogenes; Donigus, Benjamin; Dordic, Olja; Van Doremalen, Lennart Vincent; Dubey, Anand Kumar; Dubla, Andrea; Ducroux, Laurent; Dudi, Sandeep; Duggal, Ashpreet Kaur; Dukhishyam, Mallick; Dupieux, Pascal; Ehlers Iii, Raymond James; Elia, Domenico; Endress, Eric; Engel, Heiko; Epple, Eliane; Erazmus, Barbara Ewa; Erhardt, Filip; Ersdal, Magnus Rentsch; Espagnon, Bruno; Eulisse, Giulio; Eum, Jongsik; Evans, David; Evdokimov, Sergey; Fabbietti, Laura; Faggin, Mattia; Faivre, Julien; Fantoni, Alessandra; Fasel, Markus; Feldkamp, Linus; Feliciello, Alessandro; Feofilov, Grigorii; Fernandez Tellez, Arturo; Ferretti, Alessandro; Festanti, Andrea; Feuillard, Victor Jose Gaston; Figiel, Jan; Araujo Silva Figueredo, Marcel; Filchagin, Sergey; Finogeev, Dmitry; Fionda, Fiorella; Floris, Michele; Foertsch, Siegfried Valentin; Foka, Panagiota; Fokin, Sergey; Fragiacomo, Enrico; Francescon, Andrea; Francisco, Audrey; Frankenfeld, Ulrich Michael; Fronze, Gabriele Gaetano; Fuchs, Ulrich; Furget, Christophe; Furs, Artur; Fusco Girard, Mario; Gaardhoeje, Jens Joergen; Gagliardi, Martino; Gago Medina, Alberto Martin; Gajdosova, Katarina; Gallio, Mauro; Duarte Galvan, Carlos; Ganoti, Paraskevi; Garabatos Cuadrado, Jose; Garcia-solis, Edmundo Javier; Garg, Kunal; Gargiulo, Corrado; Gasik, Piotr Jan; Gauger, Erin Frances; De Leone Gay, Maria Beatriz; Germain, Marie; Ghosh, Jhuma; Ghosh, Premomoy; Ghosh, Sanjay Kumar; Gianotti, Paola; Giubellino, Paolo; Giubilato, Piero; Glassel, Peter; Gomez Coral, Diego Mauricio; Gomez Ramirez, Andres; Gonzalez Zamora, Pedro; Gorbunov, Sergey; Gorlich, Lidia Maria; Gotovac, Sven; Grabski, Varlen; Graczykowski, Lukasz Kamil; Graham, Katie Leanne; Greiner, Leo Clifford; Grelli, Alessandro; Grigoras, Costin; Grigoryev, Vladislav; Grigoryan, Ara; Grigoryan, Smbat; Gronefeld, Julius Maximilian; Grosa, Fabrizio; Grosse-oetringhaus, Jan Fiete; Grosso, Raffaele; Guernane, Rachid; Guerzoni, Barbara; Guittiere, Manuel; Gulbrandsen, Kristjan Herlache; Gunji, Taku; Gupta, Anik; Gupta, Ramni; Bautista Guzman, Irais; Haake, Rudiger; Habib, Michael Karim; Hadjidakis, Cynthia Marie; Hamagaki, Hideki; Hamar, Gergoe; Hamon, Julien Charles; Haque, Md Rihan; Harris, John William; Harton, Austin Vincent; Hassan, Hadi; Hatzifotiadou, Despina; Hayashi, Shinichi; Heckel, Stefan Thomas; Hellbar, Ernst; Helstrup, Haavard; Herghelegiu, Andrei Ionut; Gonzalez Hernandez, Emma; Herrera Corral, Gerardo Antonio; Herrmann, Florian; Hetland, Kristin Fanebust; Hillemanns, Hartmut; Hills, Christopher; Hippolyte, Boris; Hohlweger, Bernhard; Horak, David; Hornung, Sebastian; Hosokawa, Ritsuya; Hristov, Peter Zahariev; Hughes, Charles; Huhn, Patrick; Humanic, Thomas; Hushnud, Hushnud; Hussain, Nur; Hussain, Tahir; Hutter, Dirk; Hwang, Dae Sung; Iddon, James Philip; Iga Buitron, Sergio Arturo; Ilkaev, Radiy; Inaba, Motoi; Ippolitov, Mikhail; Islam, Md Samsul; Ivanov, Marian; Ivanov, Vladimir; Izucheev, Vladimir; Jacak, Barbara; Jacazio, Nicolo; Jacobs, Peter Martin; Jadhav, Manoj Bhanudas; Jadlovska, Slavka; Jadlovsky, Jan; Jaelani, Syaefudin; Jahnke, Cristiane; Jakubowska, Monika Joanna; Janik, Malgorzata Anna; Pahula Hewage, Sandun; Jena, Chitrasen; Jercic, Marko; Jimenez Bustamante, Raul Tonatiuh; Jones, Peter Graham; Jusko, Anton; Kalinak, Peter; Kalweit, Alexander Philipp; Kang, Ju Hwan; Kaplin, Vladimir; Kar, Somnath; Karasu Uysal, Ayben; Karavichev, Oleg; Karavicheva, Tatiana; Karayan, Lilit; Karczmarczyk, Przemyslaw; Karpechev, Evgeny; Kebschull, Udo Wolfgang; Keidel, Ralf; Keijdener, Darius Laurens; Keil, Markus; Ketzer, Bernhard Franz; Khabanova, Zhanna; Khan, Shaista; Khan, Shuaib Ahmad; Khanzadeev, Alexei; Kharlov, Yury; Khatun, Anisa; Khuntia, Arvind; Kielbowicz, Miroslaw Marek; Kileng, Bjarte; Kim, Byungchul; Kim, Daehyeok; Kim, Dong Jo; Kim, Eun Joo; Kim, Hyeonjoong; Kim, Jinsook; Kim, Jiyoung; Kim, Minjung; Kim, Se Yong; Kim, Taesoo; Kirsch, Stefan; Kisel, Ivan; Kiselev, Sergey; Kisiel, Adam Ryszard; Kiss, Gabor; Klay, Jennifer Lynn; Klein, Carsten; Klein, Jochen; Klein-boesing, Christian; Klewin, Sebastian; Kluge, Alexander; Knichel, Michael Linus; Knospe, Anders Garritt; Kobdaj, Chinorat; Varga-kofarago, Monika; Kohler, Markus Konrad; Kollegger, Thorsten; Kondratev, Valerii; Kondratyeva, Natalia; Kondratyuk, Evgeny; Konevskikh, Artem; Konyushikhin, Maxim; Kovalenko, Oleksandr; Kovalenko, Vladimir; Kowalski, Marek; Kralik, Ivan; Kravcakova, Adela; Kreis, Lukas; Krivda, Marian; Krizek, Filip; Kruger, Mario; Kryshen, Evgeny; Krzewicki, Mikolaj; Kubera, Andrew Michael; Kucera, Vit; Kuhn, Christian Claude; Kuijer, Paulus Gerardus; Kumar, Jitendra; Kumar, Lokesh; Kumar, Shyam; Kundu, Sourav; Kurashvili, Podist; Kurepin, Alexander; Kurepin, Alexey; Kuryakin, Alexey; Kushpil, Svetlana; Kweon, Min Jung; Kwon, Youngil; La Pointe, Sarah Louise; La Rocca, Paola; Lagana Fernandes, Caio; Lai, Yue Shi; Lakomov, Igor; Langoy, Rune; Lapidus, Kirill; Lara Martinez, Camilo Ernesto; Lardeux, Antoine Xavier; Larionov, Pavel; Lattuca, Alessandra; Laudi, Elisa; Lavicka, Roman; Lea, Ramona; Leardini, Lucia; Lee, Seongjoo; Lehas, Fatiha; Lehner, Sebastian; Lehrbach, Johannes; Lemmon, Roy Crawford; Leogrande, Emilia; Leon Monzon, Ildefonso; Levai, Peter; Li, Xiaomei; Li, Xing Long; Lien, Jorgen Andre; Lietava, Roman; Lim, Bong-hwi; Lindal, Svein; Lindenstruth, Volker; Lindsay, Scott William; Lippmann, Christian; Lisa, Michael Annan; Litichevskyi, Vladyslav; Liu, Alwina; Ljunggren, Hans Martin; Llope, William; Lodato, Davide Francesco; Loginov, Vitaly; Loizides, Constantinos; Loncar, Petra; Lopez, Xavier Bernard; Lopez Torres, Ernesto; Lowe, Andrew John; Luettig, Philipp Johannes; Luhder, Jens Robert; Lunardon, Marcello; Luparello, Grazia; Lupi, Matteo; Maevskaya, Alla; Mager, Magnus; Mahmood, Sohail Musa; Maire, Antonin; Majka, Richard Daniel; Malaev, Mikhail; Malinina, Liudmila; Mal'kevich, Dmitry; Malzacher, Peter; Mamonov, Alexander; Manko, Vladislav; Manso, Franck; Manzari, Vito; Mao, Yaxian; Marchisone, Massimiliano; Mares, Jiri; Margagliotti, Giacomo Vito; Margotti, Anselmo; Margutti, Jacopo; Marin, Ana Maria; Markert, Christina; Marquard, Marco; Martin, Nicole Alice; Martinengo, Paolo; Lucio Martinez, Jose Antonio; Martinez Hernandez, Mario Ivan; Martinez-garcia, Gines; Martinez Pedreira, Miguel; Masciocchi, Silvia; Masera, Massimo; Masoni, Alberto; Massacrier, Laure Marie; Masson, Erwann; Mastroserio, Annalisa; Mathis, Andreas Michael; Toledo Matuoka, Paula Fernanda; Matyja, Adam Tomasz; Mayer, Christoph; Mazzilli, Marianna; Mazzoni, Alessandra Maria; Meddi, Franco; Melikyan, Yuri; Menchaca-rocha, Arturo Alejandro; Mercado-perez, Jorge; Meres, Michal; Mhlanga, Sibaliso; Miake, Yasuo; Micheletti, Luca; Mieskolainen, Matti Mikael; Mihaylov, Dimitar Lubomirov; Mikhaylov, Konstantin; Mischke, Andre; Miskowiec, Dariusz Czeslaw; Mitra, Jubin; Mitu, Ciprian Mihai; Mohammadi, Naghmeh; Mohanty, Auro Prasad; Mohanty, Bedangadas; Khan, Mohammed Mohisin; Moreira De Godoy, Denise Aparecida; Perez Moreno, Luis Alberto; Moretto, Sandra; Morreale, Astrid; Morsch, Andreas; Muccifora, Valeria; Mudnic, Eugen; Muhlheim, Daniel Michael; Muhuri, Sanjib; Mukherjee, Maitreyee; Mulligan, James Declan; Gameiro Munhoz, Marcelo; Munning, Konstantin; Arratia Munoz, Miguel Ignacio; Munzer, Robert Helmut; Murakami, Hikari; Murray, Sean; Musa, Luciano; Musinsky, Jan; Myers, Corey James; Myrcha, Julian Wojciech; Naik, Bharati; Nair, Rahul; Nandi, Basanta Kumar; Nania, Rosario; Nappi, Eugenio; Narayan, Amrendra; Naru, Muhammad Umair; Ferreira Natal Da Luz, Pedro Hugo; Nattrass, Christine; Rosado Navarro, Sebastian; Nayak, Kishora; Nayak, Ranjit; Nayak, Tapan Kumar; Nazarenko, Sergey; Negrao De Oliveira, Renato Aparecido; Nellen, Lukas; Nesbo, Simon Voigt; Neskovic, Gvozden; Ng, Fabian; Nicassio, Maria; Niedziela, Jeremi; Nielsen, Borge Svane; Nikolaev, Sergey; Nikulin, Sergey; Nikulin, Vladimir; Noferini, Francesco; Nomokonov, Petr; Nooren, Gerardus; Cabanillas Noris, Juan Carlos; Norman, Jaime; Nyanin, Alexander; Nystrand, Joakim Ingemar; Oeschler, Helmut Oskar; Oh, Hoonjung; Ohlson, Alice Elisabeth; Olah, Laszlo; Oleniacz, Janusz; Oliveira Da Silva, Antonio Carlos; Oliver, Michael Henry; Onderwaater, Jacobus; Oppedisano, Chiara; Orava, Risto; Oravec, Matej; Ortiz Velasquez, Antonio; Oskarsson, Anders Nils Erik; Otwinowski, Jacek Tomasz; Oyama, Ken; Pachmayer, Yvonne Chiara; Pacik, Vojtech; Pagano, Davide; Paic, Guy; Palni, Prabhakar; Pan, Jinjin; Pandey, Ashutosh Kumar; Panebianco, Stefano; Papikyan, Vardanush; Pareek, Pooja; Park, Jonghan; Parmar, Sonia; Passfeld, Annika; Pathak, Surya Prakash; Patra, Rajendra Nath; Paul, Biswarup; Pei, Hua; Peitzmann, Thomas; Peng, Xinye; Pereira, Luis Gustavo; Pereira Da Costa, Hugo Denis Antonio; Peresunko, Dmitry Yurevich; Perez Lezama, Edgar; Peskov, Vladimir; Pestov, Yury; Petracek, Vojtech; Petrovici, Mihai; Petta, Catia; Peretti Pezzi, Rafael; Piano, Stefano; Pikna, Miroslav; Pillot, Philippe; Ozelin De Lima Pimentel, Lais; Pinazza, Ombretta; Pinsky, Lawrence; Pisano, Silvia; Piyarathna, Danthasinghe; Ploskon, Mateusz Andrzej; Planinic, Mirko; Pliquett, Fabian; Pluta, Jan Marian; Pochybova, Sona; Podesta Lerma, Pedro Luis Manuel; Poghosyan, Martin; Polishchuk, Boris; Poljak, Nikola; Poonsawat, Wanchaloem; Pop, Amalia; Poppenborg, Hendrik; Porteboeuf, Sarah Julie; Pozdniakov, Valeriy; Prasad, Sidharth Kumar; Preghenella, Roberto; Prino, Francesco; Pruneau, Claude Andre; Pshenichnov, Igor; Puccio, Maximiliano; Punin, Valery; Putschke, Jorn Henning; Raha, Sibaji; Rajput, Sonia; Rak, Jan; Rakotozafindrabe, Andry Malala; Ramello, Luciano; Rami, Fouad; Rana, Dhan Bahadur; Raniwala, Rashmi; Raniwala, Sudhir; Rasanen, Sami Sakari; Rascanu, Bogdan Theodor; Rathee, Deepika; Ratza, Viktor; Ravasenga, Ivan; Read, Kenneth Francis; Redlich, Krzysztof; Rehman, Attiq Ur; Reichelt, Patrick Simon; Reidt, Felix; Ren, Xiaowen; Renfordt, Rainer Arno Ernst; Reshetin, Andrey; Reygers, Klaus Johannes; Riabov, Viktor; Richert, Tuva Ora Herenui; Richter, Matthias Rudolph; Riedler, Petra; Riegler, Werner; Riggi, Francesco; Ristea, Catalin-lucian; Rodriguez Cahuantzi, Mario; Roeed, Ketil; Rogalev, Roman; Rogochaya, Elena; Rohr, David Michael; Roehrich, Dieter; Rokita, Przemyslaw Stefan; Ronchetti, Federico; Dominguez Rosas, Edgar; Roslon, Krystian; Rosnet, Philippe; Rossi, Andrea; Rotondi, Alberto; Roukoutakis, Filimon; Roy, Christelle Sophie; Roy, Pradip Kumar; Vazquez Rueda, Omar; Rui, Rinaldo; Rumyantsev, Boris; Rustamov, Anar; Ryabinkin, Evgeny; Ryabov, Yury; Rybicki, Andrzej; Saarinen, Sampo; Sadhu, Samrangy; Sadovskiy, Sergey; Safarik, Karel; Saha, Sumit Kumar; Sahoo, Baidyanath; Sahoo, Pragati; Sahoo, Raghunath; Sahoo, Sarita; Sahu, Pradip Kumar; Saini, Jogender; Sakai, Shingo; Saleh, Mohammad Ahmad; Sambyal, Sanjeev Singh; Samsonov, Vladimir; Sandoval, Andres; Sarkar, Amal; Sarkar, Debojit; Sarkar, Nachiketa; Sarma, Pranjal; Sas, Mike Henry Petrus; Scapparone, Eugenio; Scarlassara, Fernando; Schaefer, Brennan; Scheid, Horst Sebastian; Schiaua, Claudiu Cornel; Schicker, Rainer Martin; Schmidt, Christian Joachim; Schmidt, Hans Rudolf; Schmidt, Marten Ole; Schmidt, Martin; Schmidt, Nicolas Vincent; Schukraft, Jurgen; Schutz, Yves Roland; Schwarz, Kilian Eberhard; Schweda, Kai Oliver; Scioli, Gilda; Scomparin, Enrico; Sefcik, Michal; Seger, Janet Elizabeth; Sekiguchi, Yuko; Sekihata, Daiki; Selyuzhenkov, Ilya; Senosi, Kgotlaesele; Senyukov, Serhiy; Serradilla Rodriguez, Eulogio; Sett, Priyanka; Sevcenco, Adrian; Shabanov, Arseniy; Shabetai, Alexandre; Shahoyan, Ruben; Shaikh, Wadut; Shangaraev, Artem; Sharma, Anjali; Sharma, Ankita; Sharma, Natasha; Sheikh, Ashik Ikbal; Shigaki, Kenta; Shimomura, Maya; Shirinkin, Sergey; Shou, Qiye; Shtejer Diaz, Katherin; Sibiryak, Yury; Siddhanta, Sabyasachi; Sielewicz, Krzysztof Marek; Siemiarczuk, Teodor; Silaeva, Svetlana; Silvermyr, David Olle Rickard; Simatovic, Goran; Simonetti, Giuseppe; Singaraju, Rama Narayana; Singh, Ranbir; Singhal, Vikas; Sarkar - Sinha, Tinku; Sitar, Branislav; Sitta, Mario; Skaali, Bernhard; Slupecki, Maciej; Smirnov, Nikolai; Snellings, Raimond; Snellman, Tomas Wilhelm; Song, Jihye; Soramel, Francesca; Sorensen, Soren Pontoppidan; Sozzi, Federica; Sputowska, Iwona Anna; Stachel, Johanna; Stan, Ionel; Stankus, Paul; Stenlund, Evert Anders; Stocco, Diego; Storetvedt, Maksim Melnik; Strmen, Peter; Alarcon Do Passo Suaide, Alexandre; Sugitate, Toru; Suire, Christophe Pierre; Suleymanov, Mais Kazim Oglu; Suljic, Miljenko; Sultanov, Rishat; Sumbera, Michal; Sumowidagdo, Suharyo; Suzuki, Ken; Swain, Sagarika; Szabo, Alexander; Szarka, Imrich; Tabassam, Uzma; Takahashi, Jun; Tambave, Ganesh Jagannath; Tanaka, Naoto; Tarhini, Mohamad; Tariq, Mohammad; Tarzila, Madalina-gabriela; Tauro, Arturo; Tejeda Munoz, Guillermo; Telesca, Adriana; Terasaki, Kohei; Terrevoli, Cristina; Teyssier, Boris; Thakur, Dhananjaya; Thakur, Sanchari; Thomas, Deepa; Thoresen, Freja; Tieulent, Raphael Noel; Tikhonov, Anatoly; Timmins, Anthony Robert; Toia, Alberica; Topilskaya, Nataliya; Toppi, Marco; Rojas Torres, Solangel; Tripathy, Sushanta; Trogolo, Stefano; Trombetta, Giuseppe; Tropp, Lukas; Trubnikov, Victor; Trzaska, Wladyslaw Henryk; Trzcinski, Tomasz Piotr; Trzeciak, Barbara Antonina; Tsuji, Tomoya; Tumkin, Alexandr; Turrisi, Rosario; Tveter, Trine Spedstad; Ullaland, Kjetil; Umaka, Ejiro Naomi; Uras, Antonio; Usai, Gianluca; Utrobicic, Antonija; Vala, Martin; Van Der Maarel, Jasper; Van Hoorne, Jacobus Willem; Van Leeuwen, Marco; Vanat, Tomas; Vande Vyvre, Pierre; Varga, Dezso; Diozcora Vargas Trevino, Aurora; Vargyas, Marton; Varma, Raghava; Vasileiou, Maria; Vasiliev, Andrey; Vauthier, Astrid; Vazquez Doce, Oton; Vechernin, Vladimir; Veen, Annelies Marianne; Velure, Arild; Vercellin, Ermanno; Vergara Limon, Sergio; Vermunt, Luuk; Vernet, Renaud; Vertesi, Robert; Vickovic, Linda; Viinikainen, Jussi Samuli; Vilakazi, Zabulon; Villalobos Baillie, Orlando; Villatoro Tello, Abraham; Vinogradov, Alexander; Vinogradov, Leonid; Virgili, Tiziano; Vislavicius, Vytautas; Vodopyanov, Alexander; Volkl, Martin Andreas; Voloshin, Kirill; Voloshin, Sergey; Volpe, Giacomo; Von Haller, Barthelemy; Vorobyev, Ivan; Voscek, Dominik; Vranic, Danilo; Vrlakova, Janka; Wagner, Boris; Wang, Hongkai; Wang, Mengliang; Watanabe, Yosuke; Weber, Michael; Weber, Steffen Georg; Wegrzynek, Adam; Weiser, Dennis Franz; Wenzel, Sandro Christian; Wessels, Johannes Peter; Westerhoff, Uwe; Whitehead, Andile Mothegi; Wiechula, Jens; Wikne, Jon; Wilk, Grzegorz Andrzej; Wilkinson, Jeremy John; Willems, Guido Alexander; Williams, Crispin; Willsher, Emily; Windelband, Bernd Stefan; Witt, William Edward; Xu, Ran; Yalcin, Serpil; Yamakawa, Kosei; Yang, Ping; Yano, Satoshi; Yin, Zhongbao; Yokoyama, Hiroki; Yoo, In-kwon; Yoon, Jin Hee; Yun, Eungyu; Yurchenko, Volodymyr; Zaccolo, Valentina; Zaman, Ali; Zampolli, Chiara; Correa Zanoli, Henrique Jose; Zardoshti, Nima; Zarochentsev, Andrey; Zavada, Petr; Zavyalov, Nikolay; Zbroszczyk, Hanna Paulina; Zhalov, Mikhail; Zhang, Haitao; Zhang, Xiaoming; Zhang, Yonghong; Zhang, Zuman; Zhao, Chengxin; Zhigareva, Natalia; Zhou, Daicui; Zhou, You; Zhou, Zhuo; Zhu, Hongsheng; Zhu, Jianhui; Zhu, Ya; Zichichi, Antonino; Zimmermann, Markus Bernhard; Zinovjev, Gennady; Zmeskal, Johann; Zou, Shuguang

2018-01-01

A measurement of beauty hadron production at mid-rapidity in proton-lead collisions at a nucleon-nucleon centre-of-mass energy $\\sqrt{s_{\\rm NN}} = 5.02$ TeV is presented. The semi-inclusive decay channel of beauty hadrons into J/$\\psi$ is considered, where the J/$\\psi$ mesons are reconstructed in the dielectron decay channel at mid-rapidity down to transverse momenta of 1.3 GeV/$c$. The b$\\rm{\\overline b}$ production cross section at mid-rapidity, ${\\rm d}\\sigma_{\\rm{b\\overline b}}/{\\rm d}y$ , and the total cross section extrapolated over full phase space, $\\sigma_{\\rm{b\\overline b}}$, are obtained. This measurement is combined with results on inclusive J/$\\psi$ production to determine the prompt J/$\\psi$ cross sections. The results in p-Pb collisions are then scaled to expectations from pp collisions at the same centre-of-mass energy to derive the nuclear modification factor $R_{\\rm pPb}$, and compared to models to study possible nuclear modifications of the production induced by cold nuclear matter effects...
Making progress with the automation of systematic reviews: principles of the International Collaboration for the Automation of Systematic Reviews (ICASR).

Science.gov (United States)

Beller, Elaine; Clark, Justin; Tsafnat, Guy; Adams, Clive; Diehl, Heinz; Lund, Hans; Ouzzani, Mourad; Thayer, Kristina; Thomas, James; Turner, Tari; Xia, Jun; Robinson, Karen; Glasziou, Paul

2018-05-19

Systematic reviews (SR) are vital to health care, but have become complicated and time-consuming, due to the rapid expansion of evidence to be synthesised. Fortunately, many tasks of systematic reviews have the potential to be automated or may be assisted by automation. Recent advances in natural language processing, text mining and machine learning have produced new algorithms that can accurately mimic human endeavour in systematic review activity, faster and more cheaply. Automation tools need to be able to work together, to exchange data and results. Therefore, we initiated the International Collaboration for the Automation of Systematic Reviews (ICASR), to successfully put all the parts of automation of systematic review production together. The first meeting was held in Vienna in October 2015. We established a set of principles to enable tools to be developed and integrated into toolkits.This paper sets out the principles devised at that meeting, which cover the need for improvement in efficiency of SR tasks, automation across the spectrum of SR tasks, continuous improvement, adherence to high quality standards, flexibility of use and combining components, the need for a collaboration and varied skills, the desire for open source, shared code and evaluation, and a requirement for replicability through rigorous and open evaluation.Automation has a great potential to improve the speed of systematic reviews. Considerable work is already being done on many of the steps involved in a review. The 'Vienna Principles' set out in this paper aim to guide a more coordinated effort which will allow the integration of work by separate teams and build on the experience, code and evaluations done by the many teams working across the globe.
Completely automated nuclear reactors for long-term operation

International Nuclear Information System (INIS)

Teller, E.; Ishikawa, M.; Wood, L.

1996-01-01

The authors discuss new types of nuclear fission reactors optimized for the generation of high-temperature heat for exceedingly safe, economic, and long-duration electricity production in large, long-lived central power stations. These reactors are quite different in design, implementation and operation from conventional light-water-cooled and -moderated reactors (LWRs) currently in widespread use, which were scaled-up from submarine nuclear propulsion reactors. They feature an inexpensive initial fuel loading which lasts the entire 30-year design life of the power-plant. The reactor contains a core comprised of a nuclear ignitor and a nuclear burn-wave propagating region comprised of natural thorium or uranium, a pressure shell for coolant transport purposes, and automatic emergency heat-dumping means to obviate concerns regarding loss-of-coolant accidents during the plant's operational and post-operational life. These reactors are proposed to be situated in suitable environments at ∼100 meter depths underground, and their operation is completely automatic, with no moving parts and no human access during or after its operational lifetime, in order to avoid both error and misuse. The power plant's heat engine and electrical generator subsystems are located above-ground
Material handling for the Los Alamos National Laboratory Nuclear Storage Facility

International Nuclear Information System (INIS)

Pittman, P.; Roybal, J.; Durrer, R.; Gordon, D.

1999-01-01

This paper will present the design and application of material handling and automation systems currently being developed for the Los Alamos National Laboratory (LANL) Nuclear Material Storage Facility (NMSF) renovation project. The NMSF is a long-term storage facility for nuclear material in various forms. The material is stored within tubes in a rack called a basket. The material handling equipment range from simple lift assist devices to more sophisticated fully automated robots, and are split into three basic systems: a Vault Automation System, an NDA automation System, and a Drum handling System. The Vault Automation system provides a mechanism to handle a basket of material cans and to load/unload storage tubes within the material vault. In addition, another robot is provided to load/unload material cans within the baskets. The NDA Automation System provides a mechanism to move material within the small canister NDA laboratory and to load/unload the NDA instruments. The Drum Handling System consists of a series of off the shelf components used to assist in lifting heavy objects such as pallets of material or drums and barrels
Investigation and survey of occasions when humans saved and improved a situation where the automation was insufficient or failed

International Nuclear Information System (INIS)

Lackman, Tomas

2011-01-01

In many systems an increased level of automation implies an altered role for the human. Behind the introduction of new automation lies different automation philosophies which stretches from trying to use as much automation as possible to adding automation only as a support to human tasks in specific situations. The Swedish Radiation Safety Authority has assigned AaF-engineering to describe the current automation philosophies within the nuclear industry. The assignment also includes a survey of events in which human involvement was necessary in order to save a situation in which the automation has not been sufficient. The survey also include an analysis of these events focusing on which automation philosophy/level of automation is most appropriate for obtaining a high level of safety. In the report three events are described in which human involvement has been crucial for the successful outcome of the situation; Spain 1989, Switzerland 1996, Forsmark/Sweden 2006. These events shows that the human is one of the most vital parts of the defense in depth, hence a strong focus should be given to looking after and maintaining human abilities in order for her to be able to act safely in such situations. The events also show potential enhancement of the defense in depth through making the most of the unique human abilities of intuitive and creative thinking and acting without access to external sources of power or prearranged procedures. These abilities are affected by the levels of automation, e.g. a too high level of automation can lead to a lack in situation awareness whilst a too low level can lead to too high levels of mental workload for the operators. To avoid degradation in human abilities to safely intervene, changes in automation levels at nuclear power plants should always be preceded by an analysis of its effect on the human in the situation at hand. In order better determine the efficiency of existing methods for assessing the effects of automation on human
Rapid Prototyping of the Central Safety System for Nuclear Risk in ITER

Energy Technology Data Exchange (ETDEWEB)

Scibile, L. [ITER Organization, 13 - St. Paul lez Durance (France); Ambrosino, G.; De Tommasi, G.; Pironti, A. [Euratom-ENEA-CREATE, Universita di Napoli Federico II, Napoli (Italy)

2009-07-01

Full text of publication follows: In the current ITER Baseline design, the Central Safety System for Nuclear Risk (CSS-N) is the safety control system in charge to assure nuclear safety for the plant, personnel and environment. In particular it is envisaged that the CSS shall interface to the plant safety systems for nuclear risk and shall coordinate the individual protection provided by the intervention of these systems by the activation, where required, of additional protections. The design of such a system, together with its implementation, strongly depends on the requirements, particularly in terms of reliability. The CSS-N is a safety critical system, thus its validation and commissioning play a very important role, since the required level of reliability must be demonstrated. In such a scenario, where a new and non-conventional system has to be deployed, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the system requirements, and they will be used to test and validate the control logic. Furthermore these tools can be used to rapid design the safety system and to carry out hardware-in-the-loop (HIL) simulations, which permit to assess the performance of the control hardware against a plant simulator. Both a control system prototype and a safety system oriented plant simulator have been developed to assess first the requirements and then the performance of the CSS-N. In particular the presented SW/HW framework permits to design and verify the CSS protection logics and to test and validate these logics by means of HIL simulations. This work introduces both the prototype and plant simulator architectures, together with the methodology adopted to design and implement these validation tools. (authors)
Altering user' acceptance of automation through prior automation exposure.

Science.gov (United States)

Bekier, Marek; Molesworth, Brett R C

2017-06-01

Air navigation service providers worldwide see increased use of automation as one solution to overcome the capacity constraints imbedded in the present air traffic management (ATM) system. However, increased use of automation within any system is dependent on user acceptance. The present research sought to determine if the point at which an individual is no longer willing to accept or cooperate with automation can be manipulated. Forty participants underwent training on a computer-based air traffic control programme, followed by two ATM exercises (order counterbalanced), one with and one without the aid of automation. Results revealed after exposure to a task with automation assistance, user acceptance of high(er) levels of automation ('tipping point') decreased; suggesting it is indeed possible to alter automation acceptance. Practitioner Summary: This paper investigates whether the point at which a user of automation rejects automation (i.e. 'tipping point') is constant or can be manipulated. The results revealed after exposure to a task with automation assistance, user acceptance of high(er) levels of automation decreased; suggesting it is possible to alter automation acceptance.
Rapid nuclear reaction

International Nuclear Information System (INIS)

Marcan, P.; Beer, G.

2008-01-01

Whereas the completion of blocks 3 and 4 in Mochovce were subject to some discussion, the building of a new unit at Jaslovske Bohunice has remained unnoticed. Not even environmentalists objected. And so far the plans to build a new power plant seem to have been approved without any major discussion about whether Slovakia really needs or does not need a new nuclear power unit. Political statements about a possible future shortage of electricity were enough. The plans of private companies to build their own power plants or the possibility of decreasing the use of energy by savings were disregarded. But a clear answer to the question whether this new power unit will generate electricity for export to other countries has not yet been given. But by the end of this year the government wants to decide whether the new power plant which will cost an estimated 100 billion Slovak crowns (3.3 billions EUR) will be built from public funds in tandem with a private investor or fully financed by private capital. The name of the private investor should become known by the end of this year. (authors)
Automated solid-phase peptide synthesis to obtain therapeutic peptides

Directory of Open Access Journals (Sweden)

Veronika Mäde

2014-05-01

Full Text Available The great versatility and the inherent high affinities of peptides for their respective targets have led to tremendous progress for therapeutic applications in the last years. In order to increase the drugability of these frequently unstable and rapidly cleared molecules, chemical modifications are of great interest. Automated solid-phase peptide synthesis (SPPS offers a suitable technology to produce chemically engineered peptides. This review concentrates on the application of SPPS by Fmoc/t-Bu protecting-group strategy, which is most commonly used. Critical issues and suggestions for the synthesis are covered. The development of automated methods from conventional to essentially improved microwave-assisted instruments is discussed. In order to improve pharmacokinetic properties of peptides, lipidation and PEGylation are described as covalent conjugation methods, which can be applied by a combination of automated and manual synthesis approaches. The synthesis and application of SPPS is described for neuropeptide Y receptor analogs as an example for bioactive hormones. The applied strategies represent innovative and potent methods for the development of novel peptide drug candidates that can be manufactured with optimized automated synthesis technologies.
Technology of nuclear war

International Nuclear Information System (INIS)

Broda, E.

1973-01-01

This Article is the Note of a lecture, which was hold by Engelbert Borda at the Catholic-Theological Faculty of the University of Vienna in 27. 03. 1973. The author describes the development of modern nuclear weapon systems and the resulting war strategies. He is concerned about a possible end of the ‚balance of terror’ and the development in automation of nuclear strike back strategies. (rössner) [de
Automated Manufacturing/Robotics Technology: Certificate and Associate Degree Programs.

Science.gov (United States)

McQuay, Paul L.

A description is provided of the Automated Manufacturing/Robotics program to be offered at Delaware County Community College beginning in September 1984. Section I provides information on the use of reprogramable industrial robots in manufacturing and the rapid changes in production that can be effected through the application of automated…
RAPID AND AUTOMATED PROCESSING OF MALDI-FTICR/MS DATA FOR N-METABOLIC LABELING IN A SHOTGUN PROTEOMICS ANALYSIS.

Science.gov (United States)

Jing, Li; Amster, I Jonathan

2009-10-15

Offline high performance liquid chromatography combined with matrix assisted laser desorption and Fourier transform ion cyclotron resonance mass spectrometry (HPLC-MALDI-FTICR/MS) provides the means to rapidly analyze complex mixtures of peptides, such as those produced by proteolytic digestion of a proteome. This method is particularly useful for making quantitative measurements of changes in protein expression by using (15)N-metabolic labeling. Proteolytic digestion of combined labeled and unlabeled proteomes produces complex mixtures that with many mass overlaps when analyzed by HPLC-MALDI-FTICR/MS. A significant challenge to data analysis is the matching of pairs of peaks which represent an unlabeled peptide and its labeled counterpart. We have developed an algorithm and incorporated it into a compute program which significantly accelerates the interpretation of (15)N metabolic labeling data by automating the process of identifying unlabeled/labeled peak pairs. The algorithm takes advantage of the high resolution and mass accuracy of FTICR mass spectrometry. The algorithm is shown to be able to successfully identify the (15)N/(14)N peptide pairs and calculate peptide relative abundance ratios in highly complex mixtures from the proteolytic digest of a whole organism protein extract.
Automated aerosol sampling and analysis for the Comprehensive Test Ban Treaty

International Nuclear Information System (INIS)

Miley, H.S.; Bowyer, S.M.; Hubbard, C.W.; McKinnon, A.D.; Perkins, R.W.; Thompson, R.C.; Warner, R.A.

1998-01-01

Detecting nuclear debris from a nuclear weapon exploded in or substantially vented to the Earth's atmosphere constitutes the most certain indication that a violation of the Comprehensive Test Ban Treaty has occurred. For this reason, a radionuclide portion of the International Monitoring System is being designed and implemented. The IMS will monitor aerosols and gaseous xenon isotopes to detect atmospheric and underground tests, respectively. An automated system, the Radionuclide Aerosol Sampler/Analyzer (RASA), has been developed at Pacific Northwest National Laboratory to meet CTBT aerosol measurement requirements. This is achieved by the use of a novel sampling apparatus, a high-resolution germanium detector, and very sophisticated software. This system draws a large volume of air (∼ 20,000 m 3 /day), performs automated gamma-ray spectral measurements (MDC( 140 Ba) 3 ), and communicates this and other data to a central data facility. Automated systems offer the added benefit of rigid controls, easily implemented QA/QC procedures, and centralized depot maintenance and operation. Other types of automated communication include pull or push transmission of State-Of-Health data, commands, and configuration data. In addition, a graphical user interface, Telnet, and other interactive communications are supported over ordinary phone or network lines. This system has been the subject of a USAF commercialization effort to meet US CTBT monitoring commitments. It will also be available to other CTBT signatories and the monitoring community for various governmental, environmental, or commercial needs. The current status of the commercialization is discussed
Advanced accounting techniques in automated fuel fabrication facilities

International Nuclear Information System (INIS)

Carlson, R.L.; DeMerschman, A.W.; Engel, D.W.

1977-01-01

The accountability system being designed for automated fuel fabrication facilities will provide real-time information on all Special Nuclear Material (SNM) located in the facility. It will utilize a distributed network of microprocessors and minicomputers to monitor material movement and obtain nuclear materials measurements directly from remote, in-line Nondestructive Assay instrumentation. As SNM crosses an accounting boundary, the accountability computer will update the master files and generate audit trail records. Mass balance accounting techniques will be used around each unit process step, while item control will be used to account for encapsulated material, and SNM in transit
Automated rapid method for the determination of Ni-63 and Fe-55 in environmental samples from dismantling of nuclear facilities; Automatisiertes Schnellverfahren zur Bestimmung von Ni-63 und Fe-55 in Umweltproben aus dem Rueckbau

Energy Technology Data Exchange (ETDEWEB)

Coeguer, E.; Zoriy, M. [Forschungszentrum Juelich GmbH (Germany). Geschaeftsbereich Sicherheit und Strahlenschutz

2016-07-01

The shutdown and decommissioning of nuclear facilities is continuing in Germany. As a consequence, due to the resulting radioactive waste, it becomes more and more important to analyse the nuclides in the produced radioactive waste efficiently. Thereby a fast and reliable analysis procedure for the determination of Ni-63 and Fe-55 is needed. Therefor we developed recently a method for the determination of Ni-63 and Fe-55 in waste water based on extraction chromatography. The method was optimized in order to improve the sample preparation. The samples with usually relatively high matrix content were decomposed by wet chemical digestion. A unique feature of the current method is the use of an automated separating column module (TSM), developed in our laboratory, in order to selectively separate the radionuclides of interest. At last separated Ni-63 and Fe-55 are analyzed by means of Liquid Scintillation Counting (LSC). To validate the developed procedure synthetically prepared (doped) matrix-matched samples as well as certificated standards were analyzed. The obtained results were in a good agreement with the expected or certified values.

Automated process control system for heat-treating nuclear power station parts

International Nuclear Information System (INIS)

Afanasiadi, N.G.; Demin, V.P.; Launin, B.N.

1984-01-01

The basic factors determining the need for an automated process control system (APCS) are discussed, as are system requirements. The basic tasks solved by the system are discussed. The functional scheme for a decentralized, two-level APCS is given
Complacency and Automation Bias in the Use of Imperfect Automation.

Science.gov (United States)

Wickens, Christopher D; Clegg, Benjamin A; Vieane, Alex Z; Sebok, Angelia L

2015-08-01

We examine the effects of two different kinds of decision-aiding automation errors on human-automation interaction (HAI), occurring at the first failure following repeated exposure to correctly functioning automation. The two errors are incorrect advice, triggering the automation bias, and missing advice, reflecting complacency. Contrasts between analogous automation errors in alerting systems, rather than decision aiding, have revealed that alerting false alarms are more problematic to HAI than alerting misses are. Prior research in decision aiding, although contrasting the two aiding errors (incorrect vs. missing), has confounded error expectancy. Participants performed an environmental process control simulation with and without decision aiding. For those with the aid, automation dependence was created through several trials of perfect aiding performance, and an unexpected automation error was then imposed in which automation was either gone (one group) or wrong (a second group). A control group received no automation support. The correct aid supported faster and more accurate diagnosis and lower workload. The aid failure degraded all three variables, but "automation wrong" had a much greater effect on accuracy, reflecting the automation bias, than did "automation gone," reflecting the impact of complacency. Some complacency was manifested for automation gone, by a longer latency and more modest reduction in accuracy. Automation wrong, creating the automation bias, appears to be a more problematic form of automation error than automation gone, reflecting complacency. Decision-aiding automation should indicate its lower degree of confidence in uncertain environments to avoid the automation bias. © 2015, Human Factors and Ergonomics Society.
A fully automated contour detection algorithm the preliminary step for scatter and attenuation compensation in SPECT

International Nuclear Information System (INIS)

Younes, R.B.; Mas, J.; Bidet, R.

1988-01-01

Contour detection is an important step in information extraction from nuclear medicine images. In order to perform accurate quantitative studies in single photon emission computed tomography (SPECT) a new procedure is described which can rapidly derive the best fit contour of an attenuated medium. Some authors evaluate the influence of the detected contour on the reconstructed images with various attenuation correction techniques. Most of the methods are strongly affected by inaccurately detected contours. This approach uses the Compton window to redetermine the convex contour: It seems to be simpler and more practical in clinical SPECT studies. The main advantages of this procedure are the high speed of computation, the accuracy of the contour found and the programme's automation. Results obtained using computer simulated and real phantoms or clinical studies demonstrate the reliability of the present algorithm. (orig.)
New perspectives in nuclear imaging

International Nuclear Information System (INIS)

Wagner, H.N. Jr.

1981-01-01

In nuclear medicine, biodistribution is studied by quantitative nuclear imaging; chemistry is translated into radio-pharmacology; physics into instrumentation; and biology into physiology. Nuclear medicine can be thought of as applied physiology and physiological chemistry. The modern nuclear chemist is concerned with molecules, with relating chemical structure to biological distributions, as for iminodiacetate compounds. Using mixed ligand analysis, the hepatobiliary agent, HIDA, developed by Loberg, proved an anionic bis-complex with a charge of minus one. Further studies elsewhere showed that the co-ordination number of technetium was 5 and that an oxo-oxygen was in the apical position. From a series of analogues the amount of the complexes excreted in the bile was found to be directly proportional to the natural log of the molecular weight to charge ratio. The trend is towards the synthesis of labelled compounds whose biodistribution depends on their chemical interaction with structurally specific binding sites, i.e. receptors, enzymes or binding sites of active transport systems. Other examples include amino acids for pancreatic imaging; deoxyglucose for studies of regional brain and heart metabolism; fatty acids for studies of the heart; steroid hormones for breast tumours; and muscarinic compounds for study of the cholinergic system of the heart. Most of these compounds are labelled with 11 C, 18 F or 13 N, available only from cyclotrons, but the extension to the more widely available 123 I and sup(99m)Tc is also proceeding rapidly, stimulated chiefly by the success with the positron-emitting compounds. Advances in nuclear imaging include the development of both positron and single photon emission tomography. Biodistribution studies in man permit measurement of regional as well as global function. Improved perception is being augmented by improved quantification and automation
Development of Hardware and Software for Automated Ultrasonic Testing

International Nuclear Information System (INIS)

Choi, Sung Nam; Lee, Hee Jong; Yang, Seung Ok

2012-01-01

Nondestructive testing (NDT) for the construction and operating of NPPs plays an important role in confirming the integrity of the NPPs. Especially, Automated ultrasonic testing (AUT) is one of the primary nondestructive examination methods for in-service inspection of the welding parts in major components in NPPs. AUT is a reliable nondestructive testing because the data of AUT are saved and reviewed with other examiners. Korea Hydro and Nuclear Power-Central Research Institute (KHNP-CRI) has developed an automated ultrasonic testing (AUT) system based on a high speed pulser-receiver. In combination with the designed software and hardware architecture, this new system permits user configurations for a wide range of user-specific applications through fully automated inspections using compact portable systems with up to eight channels. This paper gives an overview of hardware (H/W) and software (S/W) for the AUT system to inspect welds in NPPs
Proposals for the Future Development of the Russian Automated Federal Information System for Nuclear Material Control and Accounting: The Universal Reporting Concept

International Nuclear Information System (INIS)

Martyanov, Alexander; Pitel, Victor; Kasumova, Leila; Babcock, Rose A.; Heinberg, Cynthia L.

2004-01-01

Development of the automated Russian Federation Federal Information System for Nuclear Material Control and Accounting (FIS) started in 1996. From the beginning, the creation of the FIS was based on the concept of obtaining data from the material balance areas of the organizations, which would enable the system to collect detailed information on nuclear material. In December 2000, the organization-level summarized reporting method was mandated by the Russian Federation and subsequently implemented for all organizations. Analysis of long-term FIS objectives, reporting by all the MBAs in Russia, showed that the present summarized reporting approach decreed by regulations posed a fair number of problems. We need alternative methods that allow the FIS to obtain more detailed information on nuclear material but which accurately reflect the technical and economic resources available to Russian organizations. One possible solution is the universal reporting method. In August 2003, the proposals of the FIS working group to transition to the universal reporting method were approved at the fourth meeting of the Joint Coordinating Committee for Implementation of the Russian Federation and U.S. Government-to-Government Agreement on Cooperation in the Area of Nuclear Material Physical Protection, Control and Accounting (JCC). One of the important elements of universal reporting is that organizations handling nuclear material will establish 'reporting areas' in cooperation with MinAtom of Russia. A reporting area may consist of one MBA, several MBAs, or even an entire organization. This paper will discuss the universal reporting concept and its major objectives and methods for the FIS.
Clinical utility of an automated instrument for gram staining single slides.

Science.gov (United States)

Baron, Ellen Jo; Mix, Samantha; Moradi, Wais

2010-06-01

Gram stains of 87 different clinical samples were prepared by the laboratory's conventional methods (automated or manual) and by a new single-slide-type automated staining instrument, GG&B AGS-1000. Gram stains from either heat- or methanol-fixed slides stained with the new instrument were easy to interpret, and results were essentially the same as those from the methanol-fixed slides prepared as a part of the routine workflow. This instrument is well suited to a rapid-response laboratory where Gram stain requests are commonly received on a stat basis.
EddyOne automated analysis of PWR/WWER steam generator tubes eddy current data

International Nuclear Information System (INIS)

Nadinic, B.; Vanjak, Z.

2004-01-01

INETEC Institute for Nuclear Technology developed software package called Eddy One which has option of automated analysis of bobbin coil eddy current data. During its development and on site use, many valuable lessons were learned which are described in this article. In accordance with previous, the following topics are covered: General requirements for automated analysis of bobbin coil eddy current data; Main approaches to automated analysis; Multi rule algorithms for data screening; Landmark detection algorithms as prerequisite for automated analysis (threshold algorithms and algorithms based on neural network principles); Field experience with Eddy One software; Development directions (use of artificial intelligence with self learning abilities for indication detection and sizing); Automated analysis software qualification; Conclusions. Special emphasis is given on results obtained on different types of steam generators, condensers and heat exchangers. Such results are then compared with results obtained by other automated software vendors giving clear advantage to INETEC approach. It has to be pointed out that INETEC field experience was collected also on WWER steam generators what is for now unique experience.(author)
SU-C-9A-02: Structured Noise Index as An Automated Quality Control for Nuclear Medicine: A Two Year Experience

Energy Technology Data Exchange (ETDEWEB)

Nelson, J; Christianson, O; Samei, E [Duke University Medical Center, Durham, NC (United States)

2014-06-01

Purpose: Flood-field uniformity evaluation is an essential element in the assessment of nuclear medicine (NM) gamma cameras. It serves as the central element of the quality control (QC) program, acquired and analyzed on a daily basis prior to clinical imaging. Uniformity images are traditionally analyzed using pixel value-based metrics which often fail to capture subtle structure and patterns caused by changes in gamma camera performance requiring additional visual inspection which is subjective and time demanding. The goal of this project was to develop and implement a robust QC metrology for NM that is effective in identifying non-uniformity issues, reporting issues in a timely manner for efficient correction prior to clinical involvement, all incorporated into an automated effortless workflow, and to characterize the program over a two year period. Methods: A new quantitative uniformity analysis metric was developed based on 2D noise power spectrum metrology and confirmed based on expert observer visual analysis. The metric, termed Structured Noise Index (SNI) was then integrated into an automated program to analyze, archive, and report on daily NM QC uniformity images. The effectiveness of the program was evaluated over a period of 2 years. Results: The SNI metric successfully identified visually apparent non-uniformities overlooked by the pixel valuebased analysis methods. Implementation of the program has resulted in nonuniformity identification in about 12% of daily flood images. In addition, due to the vigilance of staff response, the percentage of days exceeding trigger value shows a decline over time. Conclusion: The SNI provides a robust quantification of the NM performance of gamma camera uniformity. It operates seamlessly across a fleet of multiple camera models. The automated process provides effective workflow within the NM spectra between physicist, technologist, and clinical engineer. The reliability of this process has made it the preferred
Smartnotebook: A semi-automated approach to protein sequential NMR resonance assignments

International Nuclear Information System (INIS)

Slupsky, Carolyn M.; Boyko, Robert F.; Booth, Valerie K.; Sykes, Brian D.

2003-01-01

Complete and accurate NMR spectral assignment is a prerequisite for high-throughput automated structure determination of biological macromolecules. However, completely automated assignment procedures generally encounter difficulties for all but the most ideal data sets. Sources of these problems include difficulty in resolving correlations in crowded spectral regions, as well as complications arising from dynamics, such as weak or missing peaks, or atoms exhibiting more than one peak due to exchange phenomena. Smartnotebook is a semi-automated assignment software package designed to combine the best features of the automated and manual approaches. The software finds and displays potential connections between residues, while the spectroscopist makes decisions on which connection is correct, allowing rapid and robust assignment. In addition, smartnotebook helps the user fit chains of connected residues to the primary sequence of the protein by comparing the experimentally determined chemical shifts with expected shifts derived from a chemical shift database, while providing bookkeeping throughout the assignment procedure
Pilot opinions on high level flight deck automation issues: Toward the development of a design philosophy

Science.gov (United States)

Tenney, Yvette J.; Rogers, William H.; Pew, Richard W.

1995-01-01

There has been much concern in recent years about the rapid increase in automation on commercial flight decks. The survey was composed of three major sections. The first section asked pilots to rate different automation components that exist on the latest commercial aircraft regarding their obtrusiveness and the attention and effort required in using them. The second section addressed general 'automation philosophy' issues. The third section focused on issues related to levels and amount of automation. The results indicate that pilots of advanced aircraft like their automation, use it, and would welcome more automation. However, they also believe that automation has many disadvantages, especially fully autonomous automation. They want their automation to be simple and reliable and to produce predictable results. The biggest needs for higher levels of automation were in pre-flight, communication, systems management, and task management functions, planning as well as response tasks, and high workload situations. There is an irony and a challenge in the implications of these findings. On the one hand pilots would like new automation to be simple and reliable, but they need it to support the most complex part of the job--managing and planning tasks in high workload situations.
Automation strategies in five domains - A comparison of levels of automation, function allocation and visualisation of automatic functions

International Nuclear Information System (INIS)

Andersson, J.

2011-01-01

This study was conducted as a field study where control room operators and engineers from the refinery, heat and power, aviation, shipping and nuclear domain were interviewed regarding use of automation and the visualisation of automatic functions. The purpose of the study was to collect experiences and best practices from the five studied domains on levels of automation, function allocation and visualisation of automatic functions. In total, nine different control room settings were visited. The studied settings were compared using a systemic approach based on a human-machine systems model. The results show that the 'left over principle' is still the most common applied approach for function allocation but in high risk settings the decision whether to automate or not is more carefully considered. Regarding the visualisation of automatic functions, it was found that as long as each display type (process based, functional oriented, situation oriented and task based) are applied so that they correspond to the same level of abstraction as the technical system the operators mental model will be supported. No single display type can however readily match all levels of abstraction at the same time - all display types are still needed and serve different purposes. (Author)
Initial development of an automated task analysis profiling system

International Nuclear Information System (INIS)

Jorgensen, C.C.

1984-01-01

A program for automated task analysis is described. Called TAPS (task analysis profiling system), the program accepts normal English prose and outputs skills, knowledges, attitudes, and abilities (SKAAs) along with specific guidance and recommended ability measurement tests for nuclear power plant operators. A new method for defining SKAAs is presented along with a sample program output
Improving the driver-automation interaction: an approach using automation uncertainty.

Science.gov (United States)

Beller, Johannes; Heesen, Matthias; Vollrath, Mark

2013-12-01

The aim of this study was to evaluate whether communicating automation uncertainty improves the driver-automation interaction. A false system understanding of infallibility may provoke automation misuse and can lead to severe consequences in case of automation failure. The presentation of automation uncertainty may prevent this false system understanding and, as was shown by previous studies, may have numerous benefits. Few studies, however, have clearly shown the potential of communicating uncertainty information in driving. The current study fills this gap. We conducted a driving simulator experiment, varying the presented uncertainty information between participants (no uncertainty information vs. uncertainty information) and the automation reliability (high vs.low) within participants. Participants interacted with a highly automated driving system while engaging in secondary tasks and were required to cooperate with the automation to drive safely. Quantile regressions and multilevel modeling showed that the presentation of uncertainty information increases the time to collision in the case of automation failure. Furthermore, the data indicated improved situation awareness and better knowledge of fallibility for the experimental group. Consequently, the automation with the uncertainty symbol received higher trust ratings and increased acceptance. The presentation of automation uncertaintythrough a symbol improves overall driver-automation cooperation. Most automated systems in driving could benefit from displaying reliability information. This display might improve the acceptance of fallible systems and further enhances driver-automation cooperation.
Improved compliance by BPM-driven workflow automation.

Science.gov (United States)

Holzmüller-Laue, Silke; Göde, Bernd; Fleischer, Heidi; Thurow, Kerstin

2014-12-01

Using methods and technologies of business process management (BPM) for the laboratory automation has important benefits (i.e., the agility of high-level automation processes, rapid interdisciplinary prototyping and implementation of laboratory tasks and procedures, and efficient real-time process documentation). A principal goal of the model-driven development is the improved transparency of processes and the alignment of process diagrams and technical code. First experiences of using the business process model and notation (BPMN) show that easy-to-read graphical process models can achieve and provide standardization of laboratory workflows. The model-based development allows one to change processes quickly and an easy adaption to changing requirements. The process models are able to host work procedures and their scheduling in compliance with predefined guidelines and policies. Finally, the process-controlled documentation of complex workflow results addresses modern laboratory needs of quality assurance. BPMN 2.0 as an automation language to control every kind of activity or subprocess is directed to complete workflows in end-to-end relationships. BPMN is applicable as a system-independent and cross-disciplinary graphical language to document all methods in laboratories (i.e., screening procedures or analytical processes). That means, with the BPM standard, a communication method of sharing process knowledge of laboratories is also available. © 2014 Society for Laboratory Automation and Screening.
On Markov processes in the hadron-nuclear and nuclear-nuclear collisions at superhigh energies

International Nuclear Information System (INIS)

Lebedeva, A.A.; Rus'kin, V.I.

2001-01-01

In the article the possibility of the Markov processes use as simulation method for mean characteristics of hadron-nuclear and nucleus-nuclear collisions at superhigh energies is discussed. The simple (hadron-nuclear collisions) and non-simple (nucleus-nuclear collisions) non-uniform Markov process of output constant spectrum and absorption in a nucleon's nucleus-target with rapidity y are considered. The expression allowing to simulate the different collision modes were obtained
A HUMAN AUTOMATION INTERACTION CONCEPT FOR A SMALL MODULAR REACTOR CONTROL ROOM

Energy Technology Data Exchange (ETDEWEB)

Le Blanc, Katya; Spielman, Zach; Hill, Rachael

2017-06-01

Many advanced nuclear power plant (NPP) designs incorporate higher degrees of automation than the existing fleet of NPPs. Automation is being introduced or proposed in NPPs through a wide variety of systems and technologies, such as advanced displays, computer-based procedures, advanced alarm systems, and computerized operator support systems. Additionally, many new reactor concepts, both full scale and small modular reactors, are proposing increased automation and reduced staffing as part of their concept of operations. However, research consistently finds that there is a fundamental tradeoff between system performance with increased automation and reduced human performance. There is a need to address the question of how to achieve high performance and efficiency of high levels of automation without degrading human performance. One example of a new NPP concept that will utilize greater degrees of automation is the SMR concept from NuScale Power. The NuScale Power design requires 12 modular units to be operated in one single control room, which leads to a need for higher degrees of automation in the control room. Idaho National Laboratory (INL) researchers and NuScale Power human factors and operations staff are working on a collaborative project to address the human performance challenges of increased automation and to determine the principles that lead to optimal performance in highly automated systems. This paper will describe this concept in detail and will describe an experimental test of the concept. The benefits and challenges of the approach will be discussed.
A three-dimensional image processing program for accurate, rapid, and semi-automated segmentation of neuronal somata with dense neurite outgrowth

Science.gov (United States)

Ross, James D.; Cullen, D. Kacy; Harris, James P.; LaPlaca, Michelle C.; DeWeerth, Stephen P.

2015-01-01

Three-dimensional (3-D) image analysis techniques provide a powerful means to rapidly and accurately assess complex morphological and functional interactions between neural cells. Current software-based identification methods of neural cells generally fall into two applications: (1) segmentation of cell nuclei in high-density constructs or (2) tracing of cell neurites in single cell investigations. We have developed novel methodologies to permit the systematic identification of populations of neuronal somata possessing rich morphological detail and dense neurite arborization throughout thick tissue or 3-D in vitro constructs. The image analysis incorporates several novel automated features for the discrimination of neurites and somata by initially classifying features in 2-D and merging these classifications into 3-D objects; the 3-D reconstructions automatically identify and adjust for over and under segmentation errors. Additionally, the platform provides for software-assisted error corrections to further minimize error. These features attain very accurate cell boundary identifications to handle a wide range of morphological complexities. We validated these tools using confocal z-stacks from thick 3-D neural constructs where neuronal somata had varying degrees of neurite arborization and complexity, achieving an accuracy of ≥95%. We demonstrated the robustness of these algorithms in a more complex arena through the automated segmentation of neural cells in ex vivo brain slices. These novel methods surpass previous techniques by improving the robustness and accuracy by: (1) the ability to process neurites and somata, (2) bidirectional segmentation correction, and (3) validation via software-assisted user input. This 3-D image analysis platform provides valuable tools for the unbiased analysis of neural tissue or tissue surrogates within a 3-D context, appropriate for the study of multi-dimensional cell-cell and cell-extracellular matrix interactions. PMID
Determination of the nuclear incompressibility from the rapidity-dependent elliptic flow in heavy-ion collisions at beam energies 0.4A–1.0A GeV

Directory of Open Access Journals (Sweden)

Yongjia Wang

2018-03-01

Full Text Available Background: The nuclear incompressibility (K0 plays a crucial role in understanding diverse phenomena in nuclear structure and reactions, as well as in astrophysics. Heavy-ion-collision measurements in combination with transport model simulations serve as important tools for extracting the nuclear incompressibility. However, uncertainties in transport models (or model dependence partly affect the reliability of the extracted result. Purpose: In the present work, by using the recently measured data of rapidity-dependent flows, we constrain the incompressibility of nuclear matter and analyze the impact of model uncertainties on the obtained value. Method: The method is based on the newly updated version of the ultrarelativistic quantum molecular dynamics (UrQMD model in which the Skyrme potential energy-density functional is introduced. Three different Skyrme interactions which give different incompressibilities varying from K0=201 to 271 MeV are adopted. The incompressibility is deduced from the comparison of the UrQMD model simulations and the FOPI data for rapidity-dependent elliptic flow in Au+Au collisions at beam energies 0.4A–1.0A GeV. Results: The elliptic flow v2 as a function of rapidity y0 can be well described by a quadratic fit v2=v20+v22⋅y02. It is found that the quantity v2n defined by v2n=|v20|+|v22| is quite sensitive to the incompressibility K0 and the in-medium nucleon–nucleon cross section, but not sensitive to the slope parameter L of the nuclear symmetry energy. Conclusions: With the FU3FP4 parametrization of the in-medium nucleon–nucleon cross section, an averaged K0=220±40 MeV is extracted from the v2n of free protons and deuterons. However, remaining systematic uncertainties, partly related to the choice of in-medium nucleon–nucleon cross sections, are of the same magnitude (±40 MeV. Overall, the rapidity dependent elliptic flow supports a soft symmetric-matter equation-of-state.
Determination of the nuclear incompressibility from the rapidity-dependent elliptic flow in heavy-ion collisions at beam energies 0.4A-1.0A GeV

Science.gov (United States)

Wang, Yongjia; Guo, Chenchen; Li, Qingfeng; Le Fèvre, Arnaud; Leifels, Yvonne; Trautmann, Wolfgang

2018-03-01

Background: The nuclear incompressibility (K0) plays a crucial role in understanding diverse phenomena in nuclear structure and reactions, as well as in astrophysics. Heavy-ion-collision measurements in combination with transport model simulations serve as important tools for extracting the nuclear incompressibility. However, uncertainties in transport models (or model dependence) partly affect the reliability of the extracted result. Purpose: In the present work, by using the recently measured data of rapidity-dependent flows, we constrain the incompressibility of nuclear matter and analyze the impact of model uncertainties on the obtained value. Method: The method is based on the newly updated version of the ultrarelativistic quantum molecular dynamics (UrQMD) model in which the Skyrme potential energy-density functional is introduced. Three different Skyrme interactions which give different incompressibilities varying from K0 = 201 to 271 MeV are adopted. The incompressibility is deduced from the comparison of the UrQMD model simulations and the FOPI data for rapidity-dependent elliptic flow in Au + Au collisions at beam energies 0.4A-1.0A GeV. Results: The elliptic flow v2 as a function of rapidity y0 can be well described by a quadratic fit v2 =v20 +v22 ṡ y02 . It is found that the quantity v2n defined by v2n = |v20 | + |v22 | is quite sensitive to the incompressibility K0 and the in-medium nucleon-nucleon cross section, but not sensitive to the slope parameter L of the nuclear symmetry energy. Conclusions: With the FU3FP4 parametrization of the in-medium nucleon-nucleon cross section, an averaged K0 = 220 ± 40 MeV is extracted from the v2n of free protons and deuterons. However, remaining systematic uncertainties, partly related to the choice of in-medium nucleon-nucleon cross sections, are of the same magnitude (± 40 MeV). Overall, the rapidity dependent elliptic flow supports a soft symmetric-matter equation-of-state.

Rapid and fully automated Measurement of Water Vapor Sorption Isotherms

DEFF Research Database (Denmark)

Arthur, Emmanuel; Tuller, Markus; Møldrup, Per

2014-01-01

Eminent environmental challenges such as remediation of contaminated sites, the establishment and maintenance of nuclear waste repositories, or the design of surface landfill covers all require accurate quantification of the soil water characteristic at low water contents. Furthermore, several...
Research on applicability of optical and digital technologies to nuclear power stations

International Nuclear Information System (INIS)

Emoto, Motonori

1990-01-01

Recently, the development of electronic technology represented by optical multiple transmission technology and digital technology is remarkable, and it is expected that this tendency advances further hereafter. The improvement of the reliability, operational performance and maintainability of nuclear power stations by applying these most advanced technologies to them has been desired. In this research, it was found that by the application of optical multiple transmission and digital technology to nuclear power stations, their operation by a small number of operators, the automation of work management and so on can be realized. Besides, it was found that as the major technologies of hereafter, the advance of artificial intelligence technology, rapid and large capacity information processing, the network of the computers of different types and others is necessary. Further, if these technologies are completed, the clarification of the requirement when those are actually applied to nuclear power stations is necessary, and it was found also that as the matters to be considered at that time, the extent of improvement of reliability, the reduction of risk at the time of the troubles of equipment and other fundamental matters must be clarified hereafter. (K.I.)
Semi-automated delineation of breast cancer tumors and subsequent materialization using three-dimensional printing (rapid prototyping).

Science.gov (United States)

Schulz-Wendtland, Rüdiger; Harz, Markus; Meier-Meitinger, Martina; Brehm, Barbara; Wacker, Till; Hahn, Horst K; Wagner, Florian; Wittenberg, Thomas; Beckmann, Matthias W; Uder, Michael; Fasching, Peter A; Emons, Julius

2017-03-01

Three-dimensional (3D) printing has become widely available, and a few cases of its use in clinical practice have been described. The aim of this study was to explore facilities for the semi-automated delineation of breast cancer tumors and to assess the feasibility of 3D printing of breast cancer tumors. In a case series of five patients, different 3D imaging methods-magnetic resonance imaging (MRI), digital breast tomosynthesis (DBT), and 3D ultrasound-were used to capture 3D data for breast cancer tumors. The volumes of the breast tumors were calculated to assess the comparability of the breast tumor models, and the MRI information was used to render models on a commercially available 3D printer to materialize the tumors. The tumor volumes calculated from the different 3D methods appeared to be comparable. Tumor models with volumes between 325 mm 3 and 7,770 mm 3 were printed and compared with the models rendered from MRI. The materialization of the tumors reflected the computer models of them. 3D printing (rapid prototyping) appears to be feasible. Scenarios for the clinical use of the technology might include presenting the model to the surgeon to provide a better understanding of the tumor's spatial characteristics in the breast, in order to improve decision-making in relation to neoadjuvant chemotherapy or surgical approaches. J. Surg. Oncol. 2017;115:238-242. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.
Automating the Coupling of ORIGEN with GADRAS via the Fallout Analysis Tool for National Technical Nuclear Forensics

International Nuclear Information System (INIS)

Monterial, Mateusz; Jodoin, Vincent J.; Lefebvre, Jordan P.; Peplow, Douglas E.; Hooper, David A.

2012-01-01

Nuclear forensic teams will be deployed to collect and evaluate fallout samples on the ground in the scenario of a low-yield nuclear detonation in a heavily populated area. Quick non-destructive methods of predicting the quality of the sample before it is analyzed in detail are essential for efficient post-event collections. In this work, the process of exporting Defense Land Fallout Interpretive Code (DELFIC) results into Gamma Detector Response and Analysis Software (GADRAS) has been automated within the Fallout Analysis Tool. This coupling allows for the simulation of detector responses to fallout samples with varying degrees of fractionation. The degree to which the samples are fractionated depends on the location of the samples in the fallout field. In the following study, this phenomenon is examined, as its understanding is important to the investigation of debris distribution. The simulated detector spectra from GADRAS can be used to compare peak ratios of volatile-refractory isotope pairs in order to determine the degree of fractionation. Simulated fractionated fallout samples from DELFIC for a 10 kt, pure 235U fission surface burst were modeled for distances ranging to 256 km out from ground zero, and for times up to 1 week from detonation. The fractionation ratios, also known as r values, from isotope concentrations, photon lines and peak areas of four volatile-refractory pairs were calculated and compared. Fractionation prediction via the peak areas method was evaluated for each pair by comparing the results with the simulated radionuclide inventory.
Super safe small reactor RAPID-L conceptual design and R and D. JAERI's nuclear research promotion program, H11-002 (Contract research)

Energy Technology Data Exchange (ETDEWEB)

Kambe, Mitsuru [Central Research Inst. of Electric Power Industry, Tokyo (Japan); Tsunoda, Hirokazu [Mitsubishi Research Inst., Inc., Tokyo (Japan); Mishima, Kaichiro [Kyoto Univ., Kyoto (Japan); Kawasaki, Akira [Tohoku Univ., School of Engineering, Sendai, Miyagi (Japan); Iwamura, Takamichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2003-03-01

The 200 kWe uranium nitride fueled lithium cooled fast reactor 'RAPID-L' combined with thermoelectric power conversion system that can be operated unmanned without refueling for up to ten years has been demonstrated. The RAPID refueling concept enables quick and simplified refueling, and achieves plant design lifetime over 20 years. A significant advantage of the RAPID-L design, which does not require the use of control rods - is the introduction of the innovative reactivity control systems: lithium expansion module (LEM), lithium injection module (LIM) and lithium release module (LRM). LEM is the most promising candidate for improving inherent reactivity feedback. LEMs could realize burnup compensation. LIMs assure sufficient negative reactivity feedback in unprotected transients. LRMs enable an automated reactor startup by detecting the hot standby temperature of the primary coolant. All these systems use {sup 6}Li as liquid poison and are actuated by highly reliable physical properties (volume expansion of {sup 6}Li for LEM, and freeze seal melting for LIM and LRM). (author)
Guards: An approach safety-related systems using cots example of MMI and reactor automation in nuclear submarine application

International Nuclear Information System (INIS)

Brun, M.

1998-01-01

For at least 10 years, the nuclear industry designs and licences specific digital safety-critical systems (IEC 1226 class A). One key issue for future programs is to design and licence safety-related systems providing more complex functions and using Commercial-Off-The-Shelf components. This issue is especially raised for Reactor automation and Man-Machine-Interface. The usual I and C (Instrumentation and Control) organisation for these functions is based on redundancy between a commercial, up-to-date, unclassified > system and a simplified classified > system using traditional technologies. It clearly appears that such organisation is not satisfying from the point of view of people who have actually to operate these systems: The operator is supposed not to trust the normal system and rely on the back-up system which is less helpful and that he use very few. This paper presents a new approach to that problem using COTS components in low-level layers, safety architecture and mechanisms at medium level layer (GUARDS architecture developed in the current ESPRIT project number 20716), and a pre-validated functional layer. The aim of this solution is to comply with the > IEC 1226 class B requirements, at lower overall cost (design, implementation, licensing, long term confidence). This approach is illustrated by its application in Man-Machine-Interface (MMI) for our future program of Nuclear submarine. (author)
Revolutionizing our roadways : the challenges and benefits of making automated vehicles a reality.

Science.gov (United States)

2014-02-01

Automated vehicles (AVs)a combination of technologies and sensors that : enable vehicles to operate with limited or no driver inputare rapidly moving : from science fiction to real-world application. Low-level, limited function AV : technologie...
Safeguards Automated Facility Evaluation (SAFE) methodology

International Nuclear Information System (INIS)

Chapman, L.D.; Grady, L.M.; Bennett, H.A.; Sasser, D.W.; Engi, D.

1978-01-01

The SAFE procedure is an efficient method of evaluating the physical protection system of a nuclear facility. Since the algorithms used in SAFE for path generation and evaluation are analytical, many paths can be evaluated with a modest investment in computer time. SAFE is easy to use because the information required is well-defined and the interactive nature of this procedure lends itself to straightforward operation. The modular approach that has been taken allows other functionally equivalent modules to be substituted as they become available. The SAFE procedure has broad applications in the nuclear facility safeguards field as well as in the security field in general. Any fixed facility containing valuable materials or components to be protected from theft or sabotage could be analyzed using this same automated evaluation technique
Automated-biasing approach to Monte Carlo shipping-cask calculations

International Nuclear Information System (INIS)

Hoffman, T.J.; Tang, J.S.; Parks, C.V.; Childs, R.L.

1982-01-01

Computer Sciences at Oak Ridge National Laboratory, under a contract with the Nuclear Regulatory Commission, has developed the SCALE system for performing standardized criticality, shielding, and heat transfer analyses of nuclear systems. During the early phase of shielding development in SCALE, it was established that Monte Carlo calculations of radiation levels exterior to a spent fuel shipping cask would be extremely expensive. This cost can be substantially reduced by proper biasing of the Monte Carlo histories. The purpose of this study is to develop and test an automated biasing procedure for the MORSE-SGC/S module of the SCALE system
Automation of metabolic stability studies in microsomes, cytosol and plasma using a 215 Gilson liquid handler.

Science.gov (United States)

Linget, J M; du Vignaud, P

1999-05-01

A 215 Gilson liquid handler was used to automate enzymatic incubations using microsomes, cytosol and plasma. The design of automated protocols are described. They were based on the use of 96 deep well plates and on HPLC-based methods for assaying the substrate. The assessment of those protocols was made with comparison between manual and automated incubations, reliability and reproducibility of automated incubations in microsomes and cytosol. Examples of the use of those programs in metabolic studies in drug research, i.e. metabolic screening in microsomes and plasma were shown. Even rapid processes (with disappearance half lives as low as 1 min) can be analysed. This work demonstrates how stability studies can be automated to save time, render experiments involving human biological media less hazardous and may be improve inter-laboratory reproducibility.
Cockpit automation - In need of a philosophy

Science.gov (United States)

Wiener, E. L.

1985-01-01

Concern has been expressed over the rapid development and deployment of automatic devices in transport aircraft, due mainly to the human interface and particularly the role of automation in inducing human error. The paper discusses the need for coherent philosophies of automation, and proposes several approaches: (1) flight management by exception, which states that as long as a crew stays within the bounds of regulations, air traffic control and flight safety, it may fly as it sees fit; (2) exceptions by forecasting, where the use of forecasting models would predict boundary penetration, rather than waiting for it to happen; (3) goal-sharing, where a computer is informed of overall goals, and subsequently has the capability of checking inputs and aircraft position for consistency with the overall goal or intentions; and (4) artificial intelligence and expert systems, where intelligent machines could mimic human reason.
Clinical Utility of an Automated Instrument for Gram Staining Single Slides ▿

Science.gov (United States)

Baron, Ellen Jo; Mix, Samantha; Moradi, Wais

2010-01-01

Gram stains of 87 different clinical samples were prepared by the laboratory's conventional methods (automated or manual) and by a new single-slide-type automated staining instrument, GG&B AGS-1000. Gram stains from either heat- or methanol-fixed slides stained with the new instrument were easy to interpret, and results were essentially the same as those from the methanol-fixed slides prepared as a part of the routine workflow. This instrument is well suited to a rapid-response laboratory where Gram stain requests are commonly received on a stat basis. PMID:20410348
Rapid and sustained cost management

International Nuclear Information System (INIS)

Hanson, D.

2009-01-01

Accenture helps clients develop comprehensive, process-driven strategies for rapid and sustained cost management that leverage deep insights and analytics. This approach enables companies to gain operating cost advantages by rationalizing, simplifying and automating current operating capabilities. It drives structural cost advantages by optimizing business mix, capital structure, organizational structure and geographic presence. This paper discussed how successful companies achieve high performance during times of economic turmoil. It also discussed the value of the winner's strategy in terms of rapid and sustained cost management (RSCM). It discussed how Accenture operates and its leveraged capabilities, improved efficiency, margins and cash flow while maintaining customer service levels. Building structural advantage and the Accenture difference were also discussed. It was concluded that RSCM is one vital way that Accenture can help companies achieve success. 4 figs
Some Challenges in the Design of Human-Automation Interaction for Safety-Critical Systems

Science.gov (United States)

Feary, Michael S.; Roth, Emilie

2014-01-01

Increasing amounts of automation are being introduced to safety-critical domains. While the introduction of automation has led to an overall increase in reliability and improved safety, it has also introduced a class of failure modes, and new challenges in risk assessment for the new systems, particularly in the assessment of rare events resulting from complex inter-related factors. Designing successful human-automation systems is challenging, and the challenges go beyond good interface development (e.g., Roth, Malin, & Schreckenghost 1997; Christoffersen & Woods, 2002). Human-automation design is particularly challenging when the underlying automation technology generates behavior that is difficult for the user to anticipate or understand. These challenges have been recognized in several safety-critical domains, and have resulted in increased efforts to develop training, procedures, regulations and guidance material (CAST, 2008, IAEA, 2001, FAA, 2013, ICAO, 2012). This paper points to the continuing need for new methods to describe and characterize the operational environment within which new automation concepts are being presented. We will describe challenges to the successful development and evaluation of human-automation systems in safety-critical domains, and describe some approaches that could be used to address these challenges. We will draw from experience with the aviation, spaceflight and nuclear power domains.
Automated spike preparation system for Isotope Dilution Mass Spectrometry (IDMS)

International Nuclear Information System (INIS)

Maxwell, S.L. III; Clark, J.P.

1990-01-01

Isotope Dilution Mass Spectrometry (IDMS) is a method frequently employed to measure dissolved, irradiated nuclear materials. A known quantity of a unique isotope of the element to be measured (referred to as the ''spike'') is added to the solution containing the analyte. The resulting solution is chemically purified then analyzed by mass spectrometry. By measuring the magnitude of the response for each isotope and the response for the ''unique spike'' then relating this to the known quantity of the ''spike'', the quantity of the nuclear material can be determined. An automated spike preparation system was developed at the Savannah River Site (SRS) to dispense spikes for use in IDMS analytical methods. Prior to this development, technicians weighed each individual spike manually to achieve the accuracy required. This procedure was time-consuming and subjected the master stock solution to evaporation. The new system employs a high precision SMI Model 300 Unipump dispenser interfaced with an electronic balance and a portable Epson HX-20 notebook computer to automate spike preparation
Automated radiometric detection of bacteria

International Nuclear Information System (INIS)

Waters, J.R.

1974-01-01

A new radiometric method called BACTEC, used for the detection of bacteria in cultures or in supposedly sterile samples, was discussed from the standpoint of methodology, both automated and semi-automated. Some of the results obtained so far were reported and some future applications and development possibilities were described. In this new method, the test sample is incubated in a sealed vial with a liquid culture medium containing a 14 C-labeled substrate. If bacteria are present, they break down the substrate, producing 14 CO 2 which is periodically extracted from the vial as a gas and is tested for radioactivity. If this gaseous radioactivity exceeds a threshold level, it is evidence of bacterial presence and growth in the test vial. The first application was for the detection of bacteria in the blood cultures of hospital patients. Data were presented showing typical results. Also discussed were future applications, such as rapid screening for bacteria in urine industrial sterility testing and the disposal of used 14 C substrates. (Mukohata, S.)
Automated fuel pin loading system

Science.gov (United States)

Christiansen, D.W.; Brown, W.F.; Steffen, J.M.

An automated loading system for nuclear reactor fuel elements utilizes a gravity feed conveyor which permits individual fuel pins to roll along a constrained path perpendicular to their respective lengths. The individual lengths of fuel cladding are directed onto movable transports, where they are aligned coaxially with the axes of associated handling equipment at appropriate production stations. Each fuel pin can be be reciprocated axially and/or rotated about its axis as required during handling steps. The fuel pins are inerted as a batch prior to welding of end caps by one of two disclosed welding systems.
Bar code usage in nuclear materials accountability

International Nuclear Information System (INIS)

Mee, W.T.

1983-01-01

The Oak Ridge Y-12 Plant began investigating the use of automated data collection devices in 1979. At this time, bar code and optical-character-recognition (OCR) systems were reviewed with the purpose of directly entering data into DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). Both of these systems appeared applicable, however, other automated devices already employed for production control made implementing the bar code and OCR seem improbable. However, the DYMCAS was placed on line for nuclear material accountability, a decision was made to consider the bar code for physical inventory listings. For the past several months a development program has been underway to use a bar code device to collect and input data to the DYMCAS on the uranium recovery operations. Programs have been completed and tested, and are being employed to ensure that data will be compatible and useful. Bar code implementation and expansion of its use for all nuclear material inventory activity in Y-12 is presented
An approach to evaluate task allocation between operators and automation with respect to safety of Nuclear Power Plants

International Nuclear Information System (INIS)

Macwan, A.; Wei, Z.G.; Wieringa, P.A.

1994-01-01

Even though the use of automation is increasing in complex systems, its effect on safety cannot be systematically analyzed using current techniques. Of particular interest is task allocation between operators and automation. In evaluating its effect on safety, a quantitative definition of degree of automation (doA) is used. The definition of doA accounts for the effect of task on safety, irrespective of whether the task is carried out by operator or automation. Also included is the indirect effect due to the change in workload perceived by the operator. This workload is translated into stress which affects operator performance, expressed as human error probability, and subsequently, safety. The approach can be useful for evaluation of existing task allocation schemes as well as in making decisions about task allocation between operators and automation. (author). 13 refs, 1 fig
Low cost automation

International Nuclear Information System (INIS)

1987-03-01

This book indicates method of building of automation plan, design of automation facilities, automation and CHIP process like basics of cutting, NC processing machine and CHIP handling, automation unit, such as drilling unit, tapping unit, boring unit, milling unit and slide unit, application of oil pressure on characteristics and basic oil pressure circuit, application of pneumatic, automation kinds and application of process, assembly, transportation, automatic machine and factory automation.

Automated x-ray spectrometer for mixed oxide pellets

International Nuclear Information System (INIS)

Lambert, M.C.; Goheen, M.W.; Urie, M.W.; Wynhoff, N.

1979-01-01

This paper discusses the development of an energy dispersive x-ray (EDX) spectrometer for the rapid, automated, close-coupled analysis of solid mixed plutonium--uranium oxide fuel pellets. Reasons are given for the system design, which is intended to give a relative precision (RSD) of +-0.3% in a total analysis time of three minutes. The principal problems in an EDX system are in maximizing the plutonium count rates
Automation strategies in five domains - A comparison of levels of automation, function allocation and visualisation of automatic functions

Energy Technology Data Exchange (ETDEWEB)

Andersson, J. (Chalmers Univ. of Technology. Division Design and Human factors. Dept. of Product and Production Development, Goeteborg (Sweden))

2011-01-15

This study was conducted as a field study where control room operators and engineers from the refinery, heat and power, aviation, shipping and nuclear domain were interviewed regarding use of automation and the visualisation of automatic functions. The purpose of the study was to collect experiences and best practices from the five studied domains on levels of automation, function allocation and visualisation of automatic functions. In total, nine different control room settings were visited. The studied settings were compared using a systemic approach based on a human-machine systems model. The results show that the 'left over principle' is still the most common applied approach for function allocation but in high risk settings the decision whether to automate or not is more carefully considered. Regarding the visualisation of automatic functions, it was found that as long as each display type (process based, functional oriented, situation oriented and task based) are applied so that they correspond to the same level of abstraction as the technical system the operator's mental model will be supported. No single display type can however readily match all levels of abstraction at the same time - all display types are still needed and serve different purposes. (Author)
Enhancing Seismic Calibration Research Through Software Automation and Scientific Information Management

Energy Technology Data Exchange (ETDEWEB)

Ruppert, S D; Dodge, D A; Ganzberger, M D; Harris, D B; Hauk, T F

2009-07-07

The National Nuclear Security Administration (NNSA) Ground-Based Nuclear Explosion Monitoring Research and Development (GNEMRD) Program at LLNL continues to make significant progress enhancing the process of deriving seismic calibrations and performing scientific integration, analysis, and information management with software automation tools. Our tool efforts address the problematic issues of very large datasets and varied formats encountered during seismic calibration research. New information management and analysis tools have resulted in demonstrated gains in efficiency of producing scientific data products and improved accuracy of derived seismic calibrations. In contrast to previous years, software development work this past year has emphasized development of automation at the data ingestion level. This change reflects a gradually-changing emphasis in our program from processing a few large data sets that result in a single integrated delivery, to processing many different data sets from a variety of sources. The increase in the number of sources had resulted in a large increase in the amount of metadata relative to the final volume of research products. Software developed this year addresses the problems of: (1) Efficient metadata ingestion and conflict resolution; (2) Automated ingestion of bulletin information; (3) Automated ingestion of waveform information from global data centers; and (4) Site Metadata and Response transformation required for certain products. This year, we also made a significant step forward in meeting a long-standing goal of developing and using a waveform correlation framework. Our objective for such a framework is to extract additional calibration data (e.g. mining blasts) and to study the extent to which correlated seismicity can be found in global and regional scale environments.
Rapid world modeling

International Nuclear Information System (INIS)

Little, Charles; Jensen, Ken

2002-01-01

Sandia National Laboratories has designed and developed systems capable of large-scale, three-dimensional mapping of unstructured environments in near real time. This mapping technique is called rapid world modeling and has proven invaluable when used by prototype systems consisting of sensory detection devices mounted on mobile platforms. These systems can be deployed into previously unmapped environments and transmit real-time 3-D visual images to operators located remotely. This paper covers a brief history of the rapid world modeling system, its implementation on mobile platforms, and the current state of the technology. Applications to the nuclear power industry are discussed. (author)
Verification and Validation in a Rapid Software Development Process

Science.gov (United States)

Callahan, John R.; Easterbrook, Steve M.

1997-01-01

The high cost of software production is driving development organizations to adopt more automated design and analysis methods such as rapid prototyping, computer-aided software engineering (CASE) tools, and high-level code generators. Even developers of safety-critical software system have adopted many of these new methods while striving to achieve high levels Of quality and reliability. While these new methods may enhance productivity and quality in many cases, we examine some of the risks involved in the use of new methods in safety-critical contexts. We examine a case study involving the use of a CASE tool that automatically generates code from high-level system designs. We show that while high-level testing on the system structure is highly desirable, significant risks exist in the automatically generated code and in re-validating releases of the generated code after subsequent design changes. We identify these risks and suggest process improvements that retain the advantages of rapid, automated development methods within the quality and reliability contexts of safety-critical projects.
Visual interface for the automation of the instrumented pendulum of Charpy tests used in the surveillance program of reactors vessel of nuclear power plants; Interfase visual para la automatizacion del pendulo instrumentado de pruebas Charpy utilizado en el programa de vigilancia de la vasija de reactores de centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A. [ININ, Carretera Mexico-Toluca Km.36.5, Mpio. de Ocoyoacac, Estado de Mexico (Mexico)]. E-mail: asrs@nuclear.inin.mx; esm@nuclear.inin.mx; jare@nuclear.inin.mx

2004-07-01

Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)
Automated Loading and Unloading of the Stratasys FDM 1600 Rapid Prototyping System

OpenAIRE

Brockmeier, Oivind

2000-01-01

Rapid prototyping systems have advanced significantly with respect to material capabilities, fabrication speed, and surface quality. However, build jobs are still manually activated one at a time. The result is non-productive machine time whenever an operator is not at hand to make a job changeover. A low-cost auxiliary system, named Continuous Layered Manufacturing (CLM), has been developed to automatically load and unload the FDM 1600 rapid prototyping system (Stratasys, Inc.). The modifica...
Basic MR sequence parameters systematically bias automated brain volume estimation

International Nuclear Information System (INIS)

Haller, Sven; Falkovskiy, Pavel; Roche, Alexis; Marechal, Benedicte; Meuli, Reto; Thiran, Jean-Philippe; Krueger, Gunnar; Lovblad, Karl-Olof; Kober, Tobias

2016-01-01

Automated brain MRI morphometry, including hippocampal volumetry for Alzheimer disease, is increasingly recognized as a biomarker. Consequently, a rapidly increasing number of software tools have become available. We tested whether modifications of simple MR protocol parameters typically used in clinical routine systematically bias automated brain MRI segmentation results. The study was approved by the local ethical committee and included 20 consecutive patients (13 females, mean age 75.8 ± 13.8 years) undergoing clinical brain MRI at 1.5 T for workup of cognitive decline. We compared three 3D T1 magnetization prepared rapid gradient echo (MPRAGE) sequences with the following parameter settings: ADNI-2 1.2 mm iso-voxel, no image filtering, LOCAL- 1.0 mm iso-voxel no image filtering, LOCAL+ 1.0 mm iso-voxel with image edge enhancement. Brain segmentation was performed by two different and established analysis tools, FreeSurfer and MorphoBox, using standard parameters. Spatial resolution (1.0 versus 1.2 mm iso-voxel) and modification in contrast resulted in relative estimated volume difference of up to 4.28 % (p < 0.001) in cortical gray matter and 4.16 % (p < 0.01) in hippocampus. Image data filtering resulted in estimated volume difference of up to 5.48 % (p < 0.05) in cortical gray matter. A simple change of MR parameters, notably spatial resolution, contrast, and filtering, may systematically bias results of automated brain MRI morphometry of up to 4-5 %. This is in the same range as early disease-related brain volume alterations, for example, in Alzheimer disease. Automated brain segmentation software packages should therefore require strict MR parameter selection or include compensatory algorithms to avoid MR parameter-related bias of brain morphometry results. (orig.)
Basic MR sequence parameters systematically bias automated brain volume estimation

Energy Technology Data Exchange (ETDEWEB)

Haller, Sven [University of Geneva, Faculty of Medicine, Geneva (Switzerland); Affidea Centre de Diagnostique Radiologique de Carouge CDRC, Geneva (Switzerland); Falkovskiy, Pavel; Roche, Alexis; Marechal, Benedicte [Siemens Healthcare HC CEMEA SUI DI BM PI, Advanced Clinical Imaging Technology, Lausanne (Switzerland); University Hospital (CHUV), Department of Radiology, Lausanne (Switzerland); Meuli, Reto [University Hospital (CHUV), Department of Radiology, Lausanne (Switzerland); Thiran, Jean-Philippe [LTS5, Ecole Polytechnique Federale de Lausanne, Lausanne (Switzerland); Krueger, Gunnar [Siemens Medical Solutions USA, Inc., Boston, MA (United States); Lovblad, Karl-Olof [University of Geneva, Faculty of Medicine, Geneva (Switzerland); University Hospitals of Geneva, Geneva (Switzerland); Kober, Tobias [Siemens Healthcare HC CEMEA SUI DI BM PI, Advanced Clinical Imaging Technology, Lausanne (Switzerland); LTS5, Ecole Polytechnique Federale de Lausanne, Lausanne (Switzerland)

2016-11-15

Automated brain MRI morphometry, including hippocampal volumetry for Alzheimer disease, is increasingly recognized as a biomarker. Consequently, a rapidly increasing number of software tools have become available. We tested whether modifications of simple MR protocol parameters typically used in clinical routine systematically bias automated brain MRI segmentation results. The study was approved by the local ethical committee and included 20 consecutive patients (13 females, mean age 75.8 ± 13.8 years) undergoing clinical brain MRI at 1.5 T for workup of cognitive decline. We compared three 3D T1 magnetization prepared rapid gradient echo (MPRAGE) sequences with the following parameter settings: ADNI-2 1.2 mm iso-voxel, no image filtering, LOCAL- 1.0 mm iso-voxel no image filtering, LOCAL+ 1.0 mm iso-voxel with image edge enhancement. Brain segmentation was performed by two different and established analysis tools, FreeSurfer and MorphoBox, using standard parameters. Spatial resolution (1.0 versus 1.2 mm iso-voxel) and modification in contrast resulted in relative estimated volume difference of up to 4.28 % (p < 0.001) in cortical gray matter and 4.16 % (p < 0.01) in hippocampus. Image data filtering resulted in estimated volume difference of up to 5.48 % (p < 0.05) in cortical gray matter. A simple change of MR parameters, notably spatial resolution, contrast, and filtering, may systematically bias results of automated brain MRI morphometry of up to 4-5 %. This is in the same range as early disease-related brain volume alterations, for example, in Alzheimer disease. Automated brain segmentation software packages should therefore require strict MR parameter selection or include compensatory algorithms to avoid MR parameter-related bias of brain morphometry results. (orig.)
Rapid detection, characterization, and enumeration of foodborne pathogens

DEFF Research Database (Denmark)

Hoorfar, Jeffrey

2011-01-01

. The present review discusses the reasons for the increasing interest in rapid methods; current developments in the field, the research needs, and the future trends. The advent of biotechnology has introduced new technologies that led to the emergence of rapid diagnostic methods and altered food testing...... of rapid methods is for fast screening of large number of samples, where most of them are expected to be test-negative, leading to faster product release for sale. This has been the main strength of rapid methods such as real-time Polymerase Chain Reaction (PCR). Enrichment PCR, where a primary culture...... of pathogen in a contaminated product. Another key issue is automation, where the key drivers are miniaturization and multiple testing, which mean that not only one instrument is flexible enough to test for many pathogens but also many pathogens can be detected with one test. The review is mainly based...
Automated Asteroseismic Analysis of Solar-type Stars

DEFF Research Database (Denmark)

Karoff, Christoffer; Campante, T.L.; Chaplin, W.J.

2010-01-01

The rapidly increasing volume of asteroseismic observations on solar-type stars has revealed a need for automated analysis tools. The reason for this is not only that individual analyses of single stars are rather time consuming, but more importantly that these large volumes of observations open...... are calculated in a consistent way. Here we present a set of automated asterosesimic analysis tools. The main engine of these set of tools is an algorithm for modelling the autocovariance spectra of the stellar acoustic spectra allowing us to measure not only the frequency of maximum power and the large......, radius, luminosity, effective temperature, surface gravity and age based on grid modeling. All the tools take into account the window function of the observations which means that they work equally well for space-based photometry observations from e.g. the NASA Kepler satellite and ground-based velocity...
Preliminary design of a production automation framework for a pyroprocessing facility

Directory of Open Access Journals (Sweden)

Moonsoo Shin

2018-04-01

Full Text Available Pyroprocessing technology has been regarded as a promising solution for recycling spent fuel in nuclear power plants. The Korea Atomic Energy Research Institute has been studying the current status of equipment and facilities for pyroprocessing and found that existing facilities are manually operated; therefore, their applications have been limited to laboratory scale because of low productivity and safety concerns. To extend the pyroprocessing technology to a commercial scale, the facility, including all the processing equipment and the material-handling devices, should be enhanced in view of automation. In an automated pyroprocessing facility, a supervised control system is needed to handle and manage material flow and associated operations. This article provides a preliminary design of the supervising system for pyroprocessing. In particular, a manufacturing execution system intended for an automated pyroprocessing facility, named Pyroprocessing Execution System, is proposed, by which the overall production process is automated via systematic collaboration with a planning system and a control system. Moreover, a simulation-based prototype system is presented to illustrate the operability of the proposed Pyroprocessing Execution System, and a simulation study to demonstrate the interoperability of the material-handling equipment with processing equipment is also provided. Keywords: Manufacturing Execution System, Material-handling, Production Automation, Production Planning and Control, Pyroprocessing, Pyroprocessing Execution System
GLONASS satellite monitoring of nuclear transports

International Nuclear Information System (INIS)

Davydov, Yu.L.

2012-01-01

In 2011 Rosatom has made the decision to create the industry-wide automated system for monitoring of transports of radioactive substances (RS) and wastes (RAW), as well as hazardous loads by rail and automobile, based upon the same hardware as used by the GLONASS satellite navigation system - the so-called ASBT-GLONASS system. The new system will use the same technical infrastructure as the existing operational Automated System for Safe Transport of Nuclear Materials of Categories I and II (ASBT). The ASBT structure includes a network of control centres fitted with automation and communication hardware. In addition, ASBT includes technical complexes installed upon transport vehicles intended for nuclear material transport. In order to identify transport vehicle location, the GLONASS/GPS (GALS-P-ASBT) satellite navigational receiver device is used, it is developed especially for ASBT systems taking in account information security requirements. By now the basic software and hardware complex ASBT-GLONASS has been created (equipment to be carried on-board the transport vehicle loaded with RS and RAW, as well as the transport control stations) that supports transport monitoring and transmission of an emergency signal to control stations of companies which deal with RS and RAW transportation [ru
Development of the automated bunker door by using a microcontroller-system

Science.gov (United States)

Ahmad, M. A.; Leo, K. W.; Mohamad, G. H. P.; Ahmad, A.; Hashim, S. A.; Chulan, R. M.; Baijan, A. H.

2018-01-01

The new low energy electron beam accelerator bunker was designed and built locally to allocate a 500 keV electron beam accelerator at Block 43T in Malaysian Nuclear Agency. This bunker is equipped with a locally made radiation shielding door of 10 tons. Originally, this door is moving manually by a wheel and fitted with a gear system. However, it is still heavy and need longer time to operate it manually. To overcome those issues, a new automated control system has been designed and developed. In this paper, the complete steps and design of automated control system based on the microcontroller (PIC16F84A) is described.
Autonomy and Automation

Science.gov (United States)

Shively, Jay

2017-01-01

A significant level of debate and confusion has surrounded the meaning of the terms autonomy and automation. Automation is a multi-dimensional concept, and we propose that Remotely Piloted Aircraft Systems (RPAS) automation should be described with reference to the specific system and task that has been automated, the context in which the automation functions, and other relevant dimensions. In this paper, we present definitions of automation, pilot in the loop, pilot on the loop and pilot out of the loop. We further propose that in future, the International Civil Aviation Organization (ICAO) RPAS Panel avoids the use of the terms autonomy and autonomous when referring to automated systems on board RPA. Work Group 7 proposes to develop, in consultation with other workgroups, a taxonomy of Levels of Automation for RPAS.
Decision Making In A High-Tech World: Automation Bias and Countermeasures

Science.gov (United States)

Mosier, Kathleen L.; Skitka, Linda J.; Burdick, Mark R.; Heers, Susan T.; Rosekind, Mark R. (Technical Monitor)

1996-01-01

Automated decision aids and decision support systems have become essential tools in many high-tech environments. In aviation, for example, flight management systems computers not only fly the aircraft, but also calculate fuel efficient paths, detect and diagnose system malfunctions and abnormalities, and recommend or carry out decisions. Air Traffic Controllers will soon be utilizing decision support tools to help them predict and detect potential conflicts and to generate clearances. Other fields as disparate as nuclear power plants and medical diagnostics are similarly becoming more and more automated. Ideally, the combination of human decision maker and automated decision aid should result in a high-performing team, maximizing the advantages of additional cognitive and observational power in the decision-making process. In reality, however, the presence of these aids often short-circuits the way that even very experienced decision makers have traditionally handled tasks and made decisions, and introduces opportunities for new decision heuristics and biases. Results of recent research investigating the use of automated aids have indicated the presence of automation bias, that is, errors made when decision makers rely on automated cues as a heuristic replacement for vigilant information seeking and processing. Automation commission errors, i.e., errors made when decision makers inappropriately follow an automated directive, or automation omission errors, i.e., errors made when humans fail to take action or notice a problem because an automated aid fails to inform them, can result from this tendency. Evidence of the tendency to make automation-related omission and commission errors has been found in pilot self reports, in studies using pilots in flight simulations, and in non-flight decision making contexts with student samples. Considerable research has found that increasing social accountability can successfully ameliorate a broad array of cognitive biases and
Remote nuclear green pellet processing system

International Nuclear Information System (INIS)

Cellier, Francis.

1980-01-01

An automated system for manufacturing nuclear fuel pellets for use in nuclear fuel elements of nuclear power reactors is described. The system comprises process components arranged vertically but not directly under each other within a single enclosure. The vertical-lateral arrangement provides for gravity flow of the product from one component to the next and for removal of each component without interference with the other components. The single enclosure eliminates time consuming transfer between separate enclosures of each component while providing three-sided access to the component through glove ports. (auth)
Comparison of Automated 4D-MSPECT and Visual Analysis for Evaluating Myocardial Perfusion in Coronary Artery Disease

Directory of Open Access Journals (Sweden)

Chien-Chin Hsu

2008-09-01

Full Text Available The aim of this study was to assess the reproducibility and diagnostic performance for coronary artery disease (CAD of an automated software package, 4D-MSPECT, and compare the results with a visual approach. We enrolled 60 patients without previously known CAD, who underwent dual-isotope rest Tl-201/stress Tc-99m sestamibi myocardial perfusion imaging and subsequent coronary angiography within 3 months. The automated summed stress score (A-SSS, summed rest score (A-SRS and summed difference score (A-SDS were obtained using a 17-segment five-point scale model with 4D-MSPECT. For intraobserver and interobserver variability assessment, automated scoring was done by a nuclear medicine physician twice and by a nuclear medicine technologist. The visual summed stress score (V-SSS, summed rest score (V-SRS, and summed difference score (V-SDS were obtained by consensus of two nuclear medicine physicians. The intraobserver and interobserver agreements of automated segmental scores were excellent. The intraobserver and interobserver summed scores also correlated well. Agreements between visual and automated segmental scores were moderate (weighted κ of 0.55 and 0.50 for stress and rest images, respectively. Correlations between automated and visual summed scores were high, with correlation coefficients of 0.89, 0.85 and 0.82 for SSS, SRS and SDS, respectively (all p < 0.001. The receiver operating characteristic area under the curve for diagnosis of CAD by V-SSS, V-SDS, A-SSS and A-SDS were 0.78 ± 0.06, 0.87 ± 0.05, 0.84 ± 0.05 and 0.90 ± 0.04, respectively. A-SDS had better diagnostic performance than A-SSS and V-SSS (p = 0.043 and p = 0.032, respectively, whereas there was no statistically significant difference between A-SDS and V-SDS (p = 0.56. Using V-SDS ≥ 2 as a diagnostic threshold, the sensitivity, specificity, and accuracy for CAD were 83.7%, 76.5% and 81.7%, respectively. Using A-SDS ≥ 3 as a diagnostic threshold, the sensitivity
Babcock experience of automated ultrasonic non-destructive testing of PWR pressure vessels during manufacture

International Nuclear Information System (INIS)

Dikstra, B.J.; Farley, J.M.; Scruton, G.

1990-01-01

Major developments in ultrasonic techniques, equipment and systems for automated inspection have lead, over a period of about ten years, to the regular application of sophisticated computer-controlled systems during the manufacture of nuclear reactor pressure vessels. Ten years ago the use of procedures defined in a code such as ASME XI might have been considered sufficient, but it is now necessary, as was demonstrated by the results of the UKAEA defect detection trials and the PISC II trials, to apply more comprehensive arrays of probes and higher test sensitivities. The ultrasonic techniques selected are demonstrated to be adequate by modelling or test-block exercises, the automated systems applied are subject to stringent quality assurance testing, and very rigorous inspection procedures are used in conjunction with a high degree of automation to ensure reproducibility of inspection quality. The state-of-the-art in automated ultrasonic testing of pressure vessels by Babcock is described. Current developments by the company, including automated flaw recognition, integrated modelling of inspection capability, and the use of electronically scanned variable-angle probes are reviewed. Examples quoted include the automated ultrasonic inspections of the Sizewell B pressurized water reactor vessel. (author)
Report of the workshop on Aviation Safety/Automation Program

Science.gov (United States)

Morello, Samuel A. (Editor)

1990-01-01

As part of NASA's responsibility to encourage and facilitate active exchange of information and ideas among members of the aviation community, an Aviation Safety/Automation workshop was organized and sponsored by the Flight Management Division of NASA Langley Research Center. The one-day workshop was held on October 10, 1989, at the Sheraton Beach Inn and Conference Center in Virginia Beach, Virginia. Participants were invited from industry, government, and universities to discuss critical questions and issues concerning the rapid introduction and utilization of advanced computer-based technology into the flight deck and air traffic controller workstation environments. The workshop was attended by approximately 30 discipline experts, automation and human factors researchers, and research and development managers. The goal of the workshop was to address major issues identified by the NASA Aviation Safety/Automation Program. Here, the results of the workshop are documented. The ideas, thoughts, and concepts were developed by the workshop participants. The findings, however, have been synthesized into a final report primarily by the NASA researchers.

Applications of artificial intelligence in the U.S. nuclear industry

International Nuclear Information System (INIS)

Uhring, R.E.

1987-01-01

In the United States, the introduction of artificial intelligence (AI) into use in the nuclear power field is being carried out by a wide spectrum of organizations (i.e., nuclear equipment vendors, architect-engineer firms, universities, national laboratories, federal agencies, the electric utility industry, and small entrepreneurial groups). The most coherent of these efforts is an Electric Power Research Institute program to demonstrate the usefulness of AI in nuclear power plants (including augmenting plant automation) and an agreement with NASA to transfer the technology of their multi-year AI Core Technology in Systems Autonomy to the nuclear power industry. A few vendors are offering commercial AI products that reduce the burden on reactor operators during both normal and abnormal operation. Several AI programs at universities and national laboratories have automation as their primary focus, and individual AI projects have been initiated under the Small Business Innovative Research Program. The fundamental and synergistic relationship between training and expert systems supports the use of AI in the training of nuclear personnel
A novel, rapid and automated conductometric method to evaluate surfactant-cells interactions by means of critical micellar concentration analysis.

Science.gov (United States)

Tiecco, Matteo; Corte, Laura; Roscini, Luca; Colabella, Claudia; Germani, Raimondo; Cardinali, Gianluigi

2014-07-25

Conductometry is widely used to determine critical micellar concentration and micellar aggregates surface properties of amphiphiles. Current conductivity experiments of surfactant solutions are typically carried out by manual pipetting, yielding some tens reading points within a couple of hours. In order to study the properties of surfactant-cells interactions, each amphiphile must be tested in different conditions against several types of cells. This calls for complex experimental designs making the application of current methods seriously time consuming, especially because long experiments risk to determine alterations of cells, independently of the surfactant action. In this paper we present a novel, accurate and rapid automated procedure to obtain conductometric curves with several hundreds reading points within tens of minutes. The method was validated with surfactant solutions alone and in combination with Saccharomyces cerevisiae cells. An easy-to use R script, calculates conductometric parameters and their statistical significance with a graphic interface to visualize data and results. The validations showed that indeed the procedure works in the same manner with surfactant alone or in combination with cells, yielding around 1000 reading points within 20 min and with high accuracy, as determined by the regression analysis. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.
Using historical wafermap data for automated yield analysis

International Nuclear Information System (INIS)

Tobin, K.W.; Karnowski, T.P.; Gleason, S.S.; Jensen, D.; Lakhani, F.

1999-01-01

To be productive and profitable in a modern semiconductor fabrication environment, large amounts of manufacturing data must be collected, analyzed, and maintained. This includes data collected from in- and off-line wafer inspection systems and from the process equipment itself. This data is increasingly being used to design new processes, control and maintain tools, and to provide the information needed for rapid yield learning and prediction. Because of increasing device complexity, the amount of data being generated is outstripping the yield engineer close-quote s ability to effectively monitor and correct unexpected trends and excursions. The 1997 SIA National Technology Roadmap for Semiconductors highlights a need to address these issues through open-quotes automated data reduction algorithms to source defects from multiple data sources and to reduce defect sourcing time.close quotes SEMATECH and the Oak Ridge National Laboratory have been developing new strategies and technologies for providing the yield engineer with higher levels of assisted data reduction for the purpose of automated yield analysis. In this article, we will discuss the current state of the art and trends in yield management automation. copyright 1999 American Vacuum Society
Automated systems to identify relevant documents in product risk management

Science.gov (United States)

2012-01-01

Background Product risk management involves critical assessment of the risks and benefits of health products circulating in the market. One of the important sources of safety information is the primary literature, especially for newer products which regulatory authorities have relatively little experience with. Although the primary literature provides vast and diverse information, only a small proportion of which is useful for product risk assessment work. Hence, the aim of this study is to explore the possibility of using text mining to automate the identification of useful articles, which will reduce the time taken for literature search and hence improving work efficiency. In this study, term-frequency inverse document-frequency values were computed for predictors extracted from the titles and abstracts of articles related to three tumour necrosis factors-alpha blockers. A general automated system was developed using only general predictors and was tested for its generalizability using articles related to four other drug classes. Several specific automated systems were developed using both general and specific predictors and training sets of different sizes in order to determine the minimum number of articles required for developing such systems. Results The general automated system had an area under the curve value of 0.731 and was able to rank 34.6% and 46.2% of the total number of 'useful' articles among the first 10% and 20% of the articles presented to the evaluators when tested on the generalizability set. However, its use may be limited by the subjective definition of useful articles. For the specific automated system, it was found that only 20 articles were required to develop a specific automated system with a prediction performance (AUC 0.748) that was better than that of general automated system. Conclusions Specific automated systems can be developed rapidly and avoid problems caused by subjective definition of useful articles. Thus the efficiency of
Plant automation and CRT display system for nuclear power plants

International Nuclear Information System (INIS)

Tekiguchi, S.; Sukai, K.; Watanabe, N.; Yamasaki, M.

1987-01-01

The reliability of plant operation is greatly improved by utilizing selected data for display in real-time on the screens of 12 color CRTs in the Central Control Room and voice information. The load on operators is reduced by automated operation of plant equipment and an operation guide. Information from the power station is transmitted to an off-site location via an optical fiber data way which makes it possible to display in real-time the same CRT screens displayed in the Central Control Room
Application of microcomputer in automating microscope measurements in nuclear emulsion viewing

International Nuclear Information System (INIS)

Blaho, D.

1985-01-01

Microcomputer system MPS 8010 is described as applied to the automation of data collection and control of a microscope. The data on the measured coordinates of the microscope are recorded on paper tape and listed on a typewriter. The microcomputer system also makes possible automatic control of the microscope position by means of stepping motors according to the value read-out of the paper tape. (author)
The VirtualwindoW for nuclear applications

Energy Technology Data Exchange (ETDEWEB)

Anderson, M.O.; McKay, M.D.; Willis, W.D.

1997-08-01

Throughout the Department of Energy (DOE) complex there are numerous facilities which were constructed to research and develop nuclear materials during the cold war era. As a result, there are now many facilities such as reactors which require dismantlement and clean up. Technological advances over the past 10 years have significantly increased the state of computers, electronics and automated machinery. Because of this rapid growth, the technology of robotics has played a key role in clean up and remote operations. While robotic systems which perform hazardous tasks are being advanced, the human interface has not. Only within the past few years has the human/machine interface been addressed. A growing concern with the rapid advances in technology is that the robotic systems will become so complex that operators will be overwhelmed by the complexity and number of controls. Thus there is an on going effort within the remote and teleoperated robotic field to develop better man-machine interfaces. The Department of Energy`s Idaho National Engineering Laboratory (INEL) has been researching methods to simplify this interface including telepresence techniques which are applicable to nuclear environments. Initial telepresence research conducted at the INEL developed a concept called the VirtualwindoW. This system minimizes the complexity of remote stereo viewing controls and provides the operator the `feel` of viewing the environment in a natural setting. The VirtualwindoW has shown that the man-machine interface can be simplified while increasing operator performance. This paper deals with the continuing research and development of the VirtualwindoW system to provide a standard camera interface. An application of the VirtualwindoW in the dismantlement of the Chicago Pile-Five (CP-5) reactor at Argonne National Laboratory-East is discussed.
The Virtualwindo W for nuclear applications

International Nuclear Information System (INIS)

Anderson, M.O.; McKay, M.D.; Willis, W.D.

1997-01-01

Throughout the Department of Energy (DOE) complex there are numerous facilities which were constructed to research and develop nuclear materials during the cold war era. As a result, there are now many facilities such as reactors which require dismantlement and clean up. Technological advances over the past 10 years have significantly increased the state of computers, electronics and automated machinery. Because of this rapid growth, the technology of robotics has played a key role in clean up and remote operations. While robotic systems which perform hazardous tasks are being advanced, the human interface has not. Only within the past few years has the human/machine interface been addressed. A growing concern with the rapid advances in technology is that the robotic systems will become so complex that operators will be overwhelmed by the complexity and number of controls. Thus there is an on going effort within the remote and teleoperated robotic field to develop better man-machine interfaces. The Department of Energy's Idaho National Engineering Laboratory (INEL) has been researching methods to simplify this interface including telepresence techniques which are applicable to nuclear environments. Initial telepresence research conducted at the INEL developed a concept called the VirtualwindoW. This system minimizes the complexity of remote stereo viewing controls and provides the operator the 'feel' of viewing the environment in a natural setting. The VirtualwindoW has shown that the man-machine interface can be simplified while increasing operator performance. This paper deals with the continuing research and development of the VirtualwindoW system to provide a standard camera interface. An application of the VirtualwindoW in the dismantlement of the Chicago Pile-Five (CP-5) reactor at Argonne National Laboratory-East is discussed
Rapid selective separation of americium/curium from simulated nuclear forensic matrices using triazine ligands

Energy Technology Data Exchange (ETDEWEB)

Higginson, Matthew A.; Livens, Francis R.; Heath, Sarah L. [Manchester Univ. (United Kingdom). Centre for Radiochemistry Research; Thompson, Paul; Marsden, Olivia J. [AWE, Aldermaston, Reading (United Kingdom); Harwood, Laurence M.; Hudson, Michael J. [Reading Univ. (United Kingdom). Dept. of Chemistry; Lewis, Frank W. [Reading Univ. (United Kingdom). Dept. of Chemistry; Northumbria Univ., Newcastle upon Tyne (United Kingdom). Dept. of Chemical and Forensic Sciences

2015-07-01

In analysis of complex nuclear forensic samples containing lanthanides, actinides and matrix elements, rapid selective extraction of Am/Cm for quantification is challenging, in particular due the difficult separation of Am/Cm from lanthanides. Here we present a separation process for Am/Cm(III) which is achieved using a combination of AG1-X8 chromatography followed by Am/Cm extraction with a triazine ligand. The ligands tested in our process were CyMe{sub 4}-BTPhen, CyMe{sub 4}-BTBP, CA-BTP and CA-BTPhen. Our process allows for purification and quantification of Am and Cm (recoveries 80% - 100%) and other major actinides in < 2 d without the use of multiple columns or thiocyanate. The process is unaffected by high level Ca(II)/Fe(III)/Al(III) (10 mg mL{sup -1}) and thus requires little pre-treatment of samples.
Costs to Automate Demand Response - Taxonomy and Results from Field Studies and Programs

Energy Technology Data Exchange (ETDEWEB)

Piette, Mary A. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Schetrit, Oren [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Kiliccote, Sila [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Cheung, Iris [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Li, Becky Z [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2017-07-31

During the past decade, the technology to automate demand response (DR) in buildings and industrial facilities has advanced significantly. Automation allows rapid, repeatable, reliable operation. This study focuses on costs for DR automation in commercial buildings with some discussion on residential buildings and industrial facilities. DR automation technology relies on numerous components, including communication systems, hardware and software gateways, standards-based messaging protocols, controls and integration platforms, and measurement and telemetry systems. This report compares cost data from several DR automation programs and pilot projects, evaluates trends in the cost per unit of DR and kilowatts (kW) available from automated systems, and applies a standard naming convention and classification or taxonomy for system elements. Median costs for the 56 installed automated DR systems studied here are about $200/kW. The deviation around this median is large with costs in some cases being an order of magnitude great or less than the median. This wide range is a result of variations in system age, size of load reduction, sophistication, and type of equipment included in cost analysis. The costs to automate fast DR systems for ancillary services are not fully analyzed in this report because additional research is needed to determine the total cost to install, operate, and maintain these systems. However, recent research suggests that they could be developed at costs similar to those of existing hot-summer DR automation systems. This report considers installation and configuration costs and does include the costs of owning and operating DR automation systems. Future analysis of the latter costs should include the costs to the building or facility manager costs as well as utility or third party program manager cost.
Automating quantum experiment control

Science.gov (United States)

Stevens, Kelly E.; Amini, Jason M.; Doret, S. Charles; Mohler, Greg; Volin, Curtis; Harter, Alexa W.

2017-03-01

The field of quantum information processing is rapidly advancing. As the control of quantum systems approaches the level needed for useful computation, the physical hardware underlying the quantum systems is becoming increasingly complex. It is already becoming impractical to manually code control for the larger hardware implementations. In this chapter, we will employ an approach to the problem of system control that parallels compiler design for a classical computer. We will start with a candidate quantum computing technology, the surface electrode ion trap, and build a system instruction language which can be generated from a simple machine-independent programming language via compilation. We incorporate compile time generation of ion routing that separates the algorithm description from the physical geometry of the hardware. Extending this approach to automatic routing at run time allows for automated initialization of qubit number and placement and additionally allows for automated recovery after catastrophic events such as qubit loss. To show that these systems can handle real hardware, we present a simple demonstration system that routes two ions around a multi-zone ion trap and handles ion loss and ion placement. While we will mainly use examples from transport-based ion trap quantum computing, many of the issues and solutions are applicable to other architectures.
Automated analysis of gastric emptying

International Nuclear Information System (INIS)

Abutaleb, A.; Frey, D.; Spicer, K.; Spivey, M.; Buckles, D.

1986-01-01

The authors devised a novel method to automate the analysis of nuclear gastric emptying studies. Many previous methods have been used to measure gastric emptying but, are cumbersome and require continuing interference by the operator to use. Two specific problems that occur are related to patient movement between images and changes in the location of the radioactive material within the stomach. Their method can be used with either dual or single phase studies. For dual phase studies the authors use In-111 labeled water and Tc-99MSC (Sulfur Colloid) labeled scrambled eggs. For single phase studies either the liquid or solid phase material is used
Home Automation

OpenAIRE

Ahmed, Zeeshan

2010-01-01

In this paper I briefly discuss the importance of home automation system. Going in to the details I briefly present a real time designed and implemented software and hardware oriented house automation research project, capable of automating house's electricity and providing a security system to detect the presence of unexpected behavior.
An automated system for the preparation of Large Size Dried (LSD) Spikes

International Nuclear Information System (INIS)

Verbruggen, A.; Bauwens, J.; Jakobsson, U.; Eykens, R.; Wellum, R.; Aregbe, Y.; Van De Steene, N.

2008-01-01

Large size dried (LSD) spikes have been produced to fulfill the existing requirement for reliable and traceable isotopic reference materials for nuclear safeguards. A system to produce certified nuclear isotopic reference material as a U/Pu mixture in the form of large size dried spikes, comparable to those produced using traditional methods has been installed in collaboration with Nucomat, a company with a recognized reputation in design and development of integrated automated systems. The major components of the system are a robot, two balances, a dispenser and a drying unit fitted into a glove box. The robot is software driven and designed to control all movements inside the glove-box, to identify unambiguously the penicillin vials with a bar-code reader, to dispense the LSD batch solution into the vials and to weigh the amount dispensed. The system functionality has been evaluated and the performance validated by comparing the results from a series of samples dispensed and weighed by the automated system with the results by manual substitution weighing. After applying the proper correction factors to the data from the automated system balance no significant difference was observed between the two. However, an additional component of uncertainty of 3*10 -4 is introduced in the uncertainty budget for the certified weights provided by the automatic system. (authors)
An automated system for the preparation of Large Size Dried (LSD) Spikes

Energy Technology Data Exchange (ETDEWEB)

Verbruggen, A.; Bauwens, J.; Jakobsson, U.; Eykens, R.; Wellum, R.; Aregbe, Y. [European Commission - Joint Research Centre, Institute for Reference Materials and Measurements (IRMM), Retieseweg 211, B2440 Geel (Belgium); Van De Steene, N. [Nucomat, Mercatorstraat 206, B9100 Sint Niklaas (Belgium)

2008-07-01

Large size dried (LSD) spikes have been produced to fulfill the existing requirement for reliable and traceable isotopic reference materials for nuclear safeguards. A system to produce certified nuclear isotopic reference material as a U/Pu mixture in the form of large size dried spikes, comparable to those produced using traditional methods has been installed in collaboration with Nucomat, a company with a recognized reputation in design and development of integrated automated systems. The major components of the system are a robot, two balances, a dispenser and a drying unit fitted into a glove box. The robot is software driven and designed to control all movements inside the glove-box, to identify unambiguously the penicillin vials with a bar-code reader, to dispense the LSD batch solution into the vials and to weigh the amount dispensed. The system functionality has been evaluated and the performance validated by comparing the results from a series of samples dispensed and weighed by the automated system with the results by manual substitution weighing. After applying the proper correction factors to the data from the automated system balance no significant difference was observed between the two. However, an additional component of uncertainty of 3*10{sup -4} is introduced in the uncertainty budget for the certified weights provided by the automatic system. (authors)
Intelligent control and automation technology for nuclear applications

International Nuclear Information System (INIS)

Kim, Jae Hee; Kim, Ko Ryeo; Lee, Jae Cheol; Eom, Heung Seop; Lee, Jang Soo

1994-01-01

Using recently established intelligent mobile robot theory and high technologies in computer science, we have designed an inspection automation system for welded parts of the reactor vessel, and we intend to establish basic technologies. The recent status of those technologies is surveyed for various application areas, and the characteristics and availability of those techniques such as intelligent mobile robot, digital computer control, intelligent user interface, realtime data processing, ultrasonic signal processing, intelligent user interface, intelligent defect recognition, are studied and examined at first. The high performance and compact size inspection system is designed, and if implemented, it is expected to be very efficient in economic point of view. In addition, the use of integrated SW system leads to the reduction of human errors. Through the analysis results and experiences, we investigated the further feasibility of basic technology applications to the various similar operation systems in NPP. (Author)
Water chemistry diagnosis system for nuclear power plants

International Nuclear Information System (INIS)

Igarashi, Hiroo; Koya, Hiroshi; Osumi, Katsumi.

1990-01-01

The water quality control for the BWRs in Japan has advanced rapidly recently, and as to the dose reduction due to the decrease of radioactivity, Japan takes the position leading the world. In the background of the advanced water quality control like this and the increase of nuclear power plants in operation, the automation of arranging a large quantity of water quality control information and the heightening of its reliability have been demanded. Hitachi group developed the water quality synthetic control system which comprises the water quality data management system to process a large quantity of water quality data with a computer and the water quality diagnosis system to evaluate the state of operation of the plants by the minute change of water quality and to carry out the operational guide in the aspect of water quality control. To this water quality diagnosis system, high speed fuzzy inference is applied in order to do rapid diagnosis with fuzzy data. The trend of development of water quality control system, the construction of the water quality synthetic control system, the configuration of the water quality diagnosis system and the development of algorithm and the improvement of the reliability of maintenance are reported. (K.I.)
Automating X-ray Fluorescence Analysis for Rapid Astrobiology Surveys.

Science.gov (United States)

Thompson, David R; Flannery, David T; Lanka, Ravi; Allwood, Abigail C; Bue, Brian D; Clark, Benton C; Elam, W Timothy; Estlin, Tara A; Hodyss, Robert P; Hurowitz, Joel A; Liu, Yang; Wade, Lawrence A

2015-11-01

A new generation of planetary rover instruments, such as PIXL (Planetary Instrument for X-ray Lithochemistry) and SHERLOC (Scanning Habitable Environments with Raman Luminescence for Organics and Chemicals) selected for the Mars 2020 mission rover payload, aim to map mineralogical and elemental composition in situ at microscopic scales. These instruments will produce large spectral cubes with thousands of channels acquired over thousands of spatial locations, a large potential science yield limited mainly by the time required to acquire a measurement after placement. A secondary bottleneck also faces mission planners after downlink; analysts must interpret the complex data products quickly to inform tactical planning for the next command cycle. This study demonstrates operational approaches to overcome these bottlenecks by specialized early-stage science data processing. Onboard, simple real-time systems can perform a basic compositional assessment, recognizing specific features of interest and optimizing sensor integration time to characterize anomalies. On the ground, statistically motivated visualization can make raw uncalibrated data products more interpretable for tactical decision making. Techniques such as manifold dimensionality reduction can help operators comprehend large databases at a glance, identifying trends and anomalies in data. These onboard and ground-side analyses can complement a quantitative interpretation. We evaluate system performance for the case study of PIXL, an X-ray fluorescence spectrometer. Experiments on three representative samples demonstrate improved methods for onboard and ground-side automation and illustrate new astrobiological science capabilities unavailable in previous planetary instruments. Dimensionality reduction-Planetary science-Visualization.
Wireless ZigBee home automation system

Science.gov (United States)

Craciunescu, Razvan; Halunga, Simona; Fratu, Octavian

2015-02-01

The home automation system concept existed for many years but in the last decade, due to the rapid development of sensors and wireless technologies, a large number of various such "intelligent homes" have been developed. The purpose of the present paper is to demonstrate the flexibility, reliability and affordability of home automation projects, based on a simple and affordable implementation. A wireless sensing and control system have been developed and tested, having a number of basic functionalities such as switching on/off the light according to ambient lighting and turning on/off the central heating. The system has been built around low power microcontrollers and ZigBee modems for wireless communication, using a set of Vishay 640 thermistor sensors for temperature measurements and Vishay LDR07 photo-resistor for humidity measurements. A trigger is activated when the temperature or light measurements are above/below a given threshold and a command is transmitted to the central unit through the ZigBee radio module. All the data processing is performed by a low power microcontroller both at the sensing device and at the control unit.
Flow injection analysis: Emerging tool for laboratory automation in radiochemistry

International Nuclear Information System (INIS)

Egorov, O.; Ruzicka, J.; Grate, J.W.; Janata, J.

1996-01-01

Automation of routine and serial assays is a common practice of modern analytical laboratory, while it is virtually nonexistent in the field of radiochemistry. Flow injection analysis (FIA) is a general solution handling methodology that has been extensively used for automation of routine assays in many areas of analytical chemistry. Reproducible automated solution handling and on-line separation capabilities are among several distinctive features that make FI a very promising, yet under utilized tool for automation in analytical radiochemistry. The potential of the technique is demonstrated through the development of an automated 90 Sr analyzer and its application in the analysis of tank waste samples from the Hanford site. Sequential injection (SI), the latest generation of FIA, is used to rapidly separate 90 Sr from interfering radionuclides and deliver separated Sr zone to a flow-through liquid scintillation detector. The separation is performed on a mini column containing Sr-specific sorbent extraction material, which selectively retains Sr under acidic conditions. The 90 Sr is eluted with water, mixed with scintillation cocktail, and sent through the flow cell of a flow through counter, where 90 Sr radioactivity is detected as a transient signal. Both peak area and peak height can be used for quantification of sample radioactivity. Alternatively, stopped flow detection can be performed to improve detection precision for low activity samples. The authors current research activities are focused on expansion of radiochemical applications of FIA methodology, with an ultimate goal of creating a set of automated methods that will cover the basic needs of radiochemical analysis at the Hanford site. The results of preliminary experiments indicate that FIA is a highly suitable technique for the automation of chemically more challenging separations, such as separation of actinide elements

An Automated Detection System for Microaneurysms That Is Effective across Different Racial Groups.

Science.gov (United States)

Saleh, George Michael; Wawrzynski, James; Caputo, Silvestro; Peto, Tunde; Al Turk, Lutfiah Ismail; Wang, Su; Hu, Yin; Da Cruz, Lyndon; Smith, Phil; Tang, Hongying Lilian

2016-01-01

Patients without diabetic retinopathy (DR) represent a large proportion of the caseload seen by the DR screening service so reliable recognition of the absence of DR in digital fundus images (DFIs) is a prime focus of automated DR screening research. We investigate the use of a novel automated DR detection algorithm to assess retinal DFIs for absence of DR. A retrospective, masked, and controlled image-based study was undertaken. 17,850 DFIs of patients from six different countries were assessed for DR by the automated system and by human graders. The system's performance was compared across DFIs from the different countries/racial groups. The sensitivities for detection of DR by the automated system were Kenya 92.8%, Botswana 90.1%, Norway 93.5%, Mongolia 91.3%, China 91.9%, and UK 90.1%. The specificities were Kenya 82.7%, Botswana 83.2%, Norway 81.3%, Mongolia 82.5%, China 83.0%, and UK 79%. There was little variability in the calculated sensitivities and specificities across the six different countries involved in the study. These data suggest the possible scalability of an automated DR detection platform that enables rapid identification of patients without DR across a wide range of races.
Extended teamwork: team performance in highly automated nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Skjerve, Ann Britt; Strand, Stine; Skraaning, Gyrd Jr.

2004-07-01

Nuclear power plant (NPP) operation is in essence a teamwork task. The central control-room (CCR) operators are required to co-operate to achieve the operational goals, and they further depend on the assistance of the field operators and, at least in modern plants, on the assistance of the high-level automatic system. Future NPPs (e.g., advanced reactors) are foreseen to contain substantially higher automation levels, reduced staffing, and redefined roles of the remaining staff, as compared to the present situation. This paper suggests that in future plants, in which the autonomy and authority of the automatic system and of the field operators are increased, the transactions between the CCR operators and automatic system/field operators might most efficiently be conceptualized within the framework of co-operation, and thus teamwork. This framework has typically been restricted to conceptualizations of the transactions between the CCR operators, but in future settings, co-ordination, communication and mutual support between the CCR operators and the field operators/automatic system may be of increased importance for sustaining plant safety, as compared to the present situation. The paper further argues that human-system interfaces in future NPPs should be designed to support the activities of the extended team consisting of the CCR operators, the field operators, and the automatic system. The paper outlines an exploratory study aimed at generating ideas on how extended teamwork quality may be promoted. The study is currently foreseen to comprise two exemplary design solutions: a state-of-the art screen-based control-room (baseline condition) and a possible future control-room in which the activities of the field operators and the automatic system are explicitly represented on the human-system interface, where the authority and autonomy of these are increased, and the staffing level reduced, as compared to the baseline condition. The study will explore extended
Extended teamwork: team performance in highly automated nuclear power plants

International Nuclear Information System (INIS)

Skjerve, Ann Britt; Strand, Stine; Skraaning, Gyrd Jr.

2004-01-01

Nuclear power plant (NPP) operation is in essence a teamwork task. The central control-room (CCR) operators are required to co-operate to achieve the operational goals, and they further depend on the assistance of the field operators and, at least in modern plants, on the assistance of the high-level automatic system. Future NPPs (e.g., advanced reactors) are foreseen to contain substantially higher automation levels, reduced staffing, and redefined roles of the remaining staff, as compared to the present situation. This paper suggests that in future plants, in which the autonomy and authority of the automatic system and of the field operators are increased, the transactions between the CCR operators and automatic system/field operators might most efficiently be conceptualized within the framework of co-operation, and thus teamwork. This framework has typically been restricted to conceptualizations of the transactions between the CCR operators, but in future settings, co-ordination, communication and mutual support between the CCR operators and the field operators/automatic system may be of increased importance for sustaining plant safety, as compared to the present situation. The paper further argues that human-system interfaces in future NPPs should be designed to support the activities of the extended team consisting of the CCR operators, the field operators, and the automatic system. The paper outlines an exploratory study aimed at generating ideas on how extended teamwork quality may be promoted. The study is currently foreseen to comprise two exemplary design solutions: a state-of-the art screen-based control-room (baseline condition) and a possible future control-room in which the activities of the field operators and the automatic system are explicitly represented on the human-system interface, where the authority and autonomy of these are increased, and the staffing level reduced, as compared to the baseline condition. The study will explore extended
Intelligent distributed control for nuclear power plants

International Nuclear Information System (INIS)

Klevans, E.H.

1992-01-01

This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Third Annual Technical Progress report summarizes the period from September 1991 to October 1992. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. His philosophy, is to improve public perception of the safety of nuclear power plants by incorporating a high degree of automation where a greatly simplified operator control console minimizes the possibility of human error in power plant operations. To achieve this goal, a hierarchically distributed control system with automated responses to plant upset conditions was pursued in this research. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 stem plant. Emphasized in this Third Annual Technical Progress Report is the continuing development of the in-plant intelligent control demonstration for the final project milestone and includes: simulation validation and the initial approach to experiment formulation
Experience based ageing analysis of NPP protection automation in Finland

International Nuclear Information System (INIS)

Simola, K.

2000-01-01

This paper describes three successive studies on ageing of protection automation of nuclear power plants. These studies were aimed at developing a methodology for an experience based ageing analysis, and applying it to identify the most critical components from ageing and safety points of view. The analyses resulted also to suggestions for improvement of data collection systems for the purpose of further ageing analyses. (author)
Cardiac imaging: working towards fully-automated machine analysis & interpretation.

Science.gov (United States)

Slomka, Piotr J; Dey, Damini; Sitek, Arkadiusz; Motwani, Manish; Berman, Daniel S; Germano, Guido

2017-03-01

Non-invasive imaging plays a critical role in managing patients with cardiovascular disease. Although subjective visual interpretation remains the clinical mainstay, quantitative analysis facilitates objective, evidence-based management, and advances in clinical research. This has driven developments in computing and software tools aimed at achieving fully automated image processing and quantitative analysis. In parallel, machine learning techniques have been used to rapidly integrate large amounts of clinical and quantitative imaging data to provide highly personalized individual patient-based conclusions. Areas covered: This review summarizes recent advances in automated quantitative imaging in cardiology and describes the latest techniques which incorporate machine learning principles. The review focuses on the cardiac imaging techniques which are in wide clinical use. It also discusses key issues and obstacles for these tools to become utilized in mainstream clinical practice. Expert commentary: Fully-automated processing and high-level computer interpretation of cardiac imaging are becoming a reality. Application of machine learning to the vast amounts of quantitative data generated per scan and integration with clinical data also facilitates a move to more patient-specific interpretation. These developments are unlikely to replace interpreting physicians but will provide them with highly accurate tools to detect disease, risk-stratify, and optimize patient-specific treatment. However, with each technological advance, we move further from human dependence and closer to fully-automated machine interpretation.
Automated long-term surveillance of a commercial nuclear power plant

International Nuclear Information System (INIS)

Smith, C.M.; Gonzalez, R.C.

1987-08-01

This report presents and describes a pattern recognition system for monitoring nuclear reactor signals. The system is based on detecting deviations from baseline signatures identified during normal plant operation. The capabilities and limitations of this pattern recognition approach were investigated during a 2-1/2-year series of continuous online experiments at the Sequoyah-1 Nuclear Power Plant
Long-term automated surveillance of a commercial nuclear power plant

International Nuclear Information System (INIS)

Smith, C.M.; Gonzalez, R.C.

1984-01-01

A pattern recognition system for monitoring nuclear reactor signals is presented. The system is based on detecting deviations from baseline signatures learned automatically during normal plant operation. The capabilities and limitations of the recognition approach were investigated during a 2-1/2-year continuous, on-line series of experiments at the Sequoyah-1 nuclear power plant
Failure mode and effects analysis of software-based automation systems

International Nuclear Information System (INIS)

Haapanen, P.; Helminen, A.

2002-08-01

Failure mode and effects analysis (FMEA) is one of the well-known analysis methods having an established position in the traditional reliability analysis. The purpose of FMEA is to identify possible failure modes of the system components, evaluate their influences on system behaviour and propose proper countermeasures to suppress these effects. The generic nature of FMEA has enabled its wide use in various branches of industry reaching from business management to the design of spaceships. The popularity and diverse use of the analysis method has led to multiple interpretations, practices and standards presenting the same analysis method. FMEA is well understood at the systems and hardware levels, where the potential failure modes usually are known and the task is to analyse their effects on system behaviour. Nowadays, more and more system functions are realised on software level, which has aroused the urge to apply the FMEA methodology also on software based systems. Software failure modes generally are unknown - 'software modules do not fail, they only display incorrect behaviour' - and depend on dynamic behaviour of the application. These facts set special requirements on the FMEA of software based systems and make it difficult to realise. In this report the failure mode and effects analysis is studied for the use of reliability analysis of software-based systems. More precisely, the target system of FMEA is defined to be a safety-critical software-based automation application in a nuclear power plant, implemented on an industrial automation system platform. Through a literature study the report tries to clarify the intriguing questions related to the practical use of software failure mode and effects analysis. The study is a part of the research project 'Programmable Automation System Safety Integrity assessment (PASSI)', belonging to the Finnish Nuclear Safety Research Programme (FINNUS, 1999-2002). In the project various safety assessment methods and tools for
JINR rapid communications

International Nuclear Information System (INIS)

1997-01-01

The present collection of rapid communications from JINR, Dubna, contains seven separate reports on investigation of the tensor analyzing power A yy in the reaction A(d polarized, p)X at large transverse momenta of proton, double-differential ionization cross section calculations for fast collisions of ions and atoms, a study of the two-photon interactions tagged at an average 2 > of 90 GeV 2 , cluster and single-particle distributions in nucleus-nucleus interactions, the Coulomb interaction of charged pions in CC-and CTa-collisions at 4.2 A GeV/c, influence of nitrogen and oxygen gas admixtures on the response of the DELPHI HCAL and MUS detectors and an automation of physics research on base of open standards
Mobile Image Ratiometry: A New Method for Instantaneous Analysis of Rapid Test Strips

OpenAIRE

Donald C. Cooper; Bryan Callahan; Phil Callahan; Lee Burnett

2012-01-01

Here we describe Mobile Image Ratiometry (MIR), a new method for the automated quantification of standardized rapid immunoassay strips using consumer-based mobile smartphone and tablet cameras. To demonstrate MIR we developed a standardized method using rapid immunotest strips directed against cocaine (COC) and its major metabolite, benzoylecgonine (BE). We performed image analysis of three brands of commercially available dye-conjugated anti-COC/BE antibody test strips in response to three d...
Comparison of two automated instruments for Epstein-Barr virus serology in a large adult hospital and implementation of an Epstein-Barr virus nuclear antigen-based testing algorithm.

Science.gov (United States)

Al Sidairi, Hilal; Binkhamis, Khalifa; Jackson, Colleen; Roberts, Catherine; Heinstein, Charles; MacDonald, Jimmy; Needle, Robert; Hatchette, Todd F; LeBlanc, Jason J

2017-11-01

Serology remains the mainstay for diagnosis of Epstein-Barr virus (EBV) infection. This study compared two automated platforms (BioPlex 2200 and Architect i2000SR) to test three EBV serological markers: viral capsid antigen (VCA) immunoglobulins of class M (IgM), VCA immunoglobulins of class G (IgG) and EBV nuclear antigen-1 (EBNA-1) IgG. Using sera from 65 patients at various stages of EBV disease, BioPlex demonstrated near-perfect agreement for all EBV markers compared to a consensus reference. The agreement for Architect was near-perfect for VCA IgG and EBNA-1 IgG, and substantial for VCA IgM despite five equivocal results. Since the majority of testing in our hospital was from adults with EBNA-1 IgG positive results, post-implementation analysis of an EBNA-based algorithm showed advantages over parallel testing of the three serologic markers. This small verification demonstrated that both automated systems for EBV serology had good performance for all EBV markers, and an EBNA-based testing algorithm is ideal for an adult hospital.
Status and trends in nuclear technology for power plants with WWER-1000 reactors. Review

Energy Technology Data Exchange (ETDEWEB)

Zorev, N N

1977-04-01

The problems of improving quality of nuclear equipment for WWER-1000 power plants and associated nuclear technology automation are surveyed. Examples of technological innovations are presented which significantly reduce labour intensity, time consumption and increase quality standards of the products. Some new automated equipments for materials welding, working, machining and quality control are described. The discussion is centering around heavy-section steel technologies. Some mechanical properties of new-developed nuclear grade steels designed for producing reactor vessels and steamgenerators, volume compensators and pipes, as well as steam separators and steamsuperheaters are also presented. Their properties (impact strength and radiation resistance) are pointed out to be superior to that of steels used abroad. The basic trend in nuclear structural material developments is towards integrated optimization of strength, performance and workability.
Fault tolerant strategies for automated operation of nuclear reactors

International Nuclear Information System (INIS)

Berkan, R.C.; Tsoukalas, L.

1991-01-01

This paper introduces an automatic control system incorporating a number of verification, validation, and command generation tasks with-in a fault-tolerant architecture. The integrated system utilizes recent methods of artificial intelligence such as neural networks and fuzzy logic control. Furthermore, advanced signal processing and nonlinear control methods are also included in the design. The primary goal is to create an on-line capability to validate signals, analyze plant performance, and verify the consistency of commands before control decisions are finalized. The application of this approach to the automated startup of the Experimental Breeder Reactor-II (EBR-II) is performed using a validated nonlinear model. The simulation results show that the advanced concepts have the potential to improve plant availability andsafety
Application of modern autoradiography to nuclear forensic analysis.

Science.gov (United States)

Parsons-Davis, Tashi; Knight, Kim; Fitzgerald, Marc; Stone, Gary; Caldeira, Lee; Ramon, Christina; Kristo, Michael

2018-05-01

Modern autoradiography techniques based on phosphorimaging technology using image plates (IPs) and digital scanning can identify heterogeneities in activity distributions and reveal material properties, serving to inform subsequent analyses. Here, we have adopted these advantages for applications in nuclear forensics, the technical analysis of radioactive or nuclear materials found outside of legal control to provide data related to provenance, production history, and trafficking route for the materials. IP autoradiography is a relatively simple, non-destructive method for sample characterization that records an image reflecting the relative intensity of alpha and beta emissions from a two-dimensional surface. Such data are complementary to information gathered from radiochemical characterization via bulk counting techniques, and can guide the application of other spatially resolved techniques such as scanning electron microscopy (SEM) and secondary ion mass spectrometry (SIMS). IP autoradiography can image large 2-dimenstional areas (up to 20×40cm), with relatively low detection limits for actinides and other radioactive nuclides, and sensitivity to a wide dynamic range (10 5 ) of activity density in a single image. Distributions of radioactivity in nuclear materials can be generated with a spatial resolution of approximately 50μm using IP autoradiography and digital scanning. While the finest grain silver halide films still provide the best possible resolution (down to ∼10μm), IP autoradiography has distinct practical advantages such as shorter exposure times, no chemical post-processing, reusability, rapid plate scanning, and automated image digitization. Sample preparation requirements are minimal, and the analytical method does not consume or alter the sample. These advantages make IP autoradiography ideal for routine screening of nuclear materials, and for the identification of areas of interest for subsequent micro-characterization methods. In this
Lab-on-a-Chip Device for Rapid Measurement of Vitamin D Levels.

Science.gov (United States)

Peter, Harald; Bistolas, Nikitas; Schumacher, Soeren; Laurisch, Cecilia; Guest, Paul C; Höller, Ulrich; Bier, Frank F

2018-01-01

Lab-on-a-chip assays allow rapid analysis of one or more molecular analytes on an automated user-friendly platform. Here we describe a fully automated assay and readout for measurement of vitamin D levels in less than 15 min using the Fraunhofer in vitro diagnostics platform. Vitamin D (25-hydroxyvitamin D 3 [25(OH)D 3 ]) dilution series in buffer were successfully tested down to 2 ng/mL. This could be applied in the future as an inexpensive point-of-care analysis for patients suffering from a variety of conditions marked by vitamin D deficiencies.
CAT: a computer code for the automated construction of fault trees

International Nuclear Information System (INIS)

Apostolakis, G.E.; Salem, S.L.; Wu, J.S.

1978-03-01

A computer code, CAT (Computer Automated Tree, is presented which applies decision table methods to model the behavior of components for systematic construction of fault trees. The decision tables for some commonly encountered mechanical and electrical components are developed; two nuclear subsystems, a Containment Spray Recirculation System and a Consequence Limiting Control System, are analyzed to demonstrate the applications of CAT code
Promoting nuclear power, achieving sustainable development of nuclear industry in China

International Nuclear Information System (INIS)

Kang, R.

2006-01-01

The past 5 decades witnessed the rapid growth of China's nuclear industry. The sustained and rapid economic growth and continuous improvement of people's living standards have placed higher requirements for energy and power supplies. As a safe and clean energy source, nuclear energy has been gradually and widely accepted by the Chinese government and the public. The Chinese government has adopted the policy a ctively pushing forward the nuclear power development , set up the target to reach 40GWe of nuclear power installed capacity by 2020, accounting for about 4% of the total installed capacity in China. In this regard, this paper presents the China's nuclear program to illustrate how China is going to achieve the target. The paper is composed of 3 parts. The first part gives a review of the achievements in nuclear power in the last 20 years. The second part presents China's ''three approach'' strategy for furthering the nuclear power development: carrying out duplication projects at the existing plant sites; introducing GUI technology via international bidding; developing the brand C NP1000 , i.e. Chinese Nuclear Power lOOOMwe class, with China's own intellectual property. This part also explores the ways of securing the fuel supply for nuclear power development. The third part concludes with CNNC's ''3221'' strategy which aims at building a world class conglomerate, and expresses its sincere wish to work with the nuclear community to push the nuclear industry worldwide by strengthening international cooperation
Simple and rapid determination methods for low-level radioactive wastes generated from nuclear research facilities. Guidelines for determination of radioactive waste samples

International Nuclear Information System (INIS)

Kameo, Yutaka; Shimada, Asako; Ishimori, Ken-ichiro; Haraga, Tomoko; Katayama, Atsushi; Nakashima, Mikio; Hoshi, Akiko

2009-10-01

Analytical methods were developed for simple and rapid determination of U, Th, and several nuclides, which are selected as important nuclides for safety assessment of disposal of wastes generated from research facilities at Nuclear Science Research Institute and Oarai Research and Development Center. The present analytical methods were assumed to apply to solidified products made from miscellaneous wastes by plasma melting in the Advanced Volume Reduction Facilities. In order to establish a system to analyze the important nuclides in the solidified products at low cost and routinely, we have advanced the development of a high-efficiency non-destructive measurement technique for γ-ray emitting nuclides, simple and rapid methods for pretreatment of solidified product samples and subsequent radiochemical separations, and rapid determination methods for long-lived nuclides. In the present paper, we summarized the methods developed as guidelines for determination of radionuclides in the low-level solidified products. (author)
A review of automated systems for cyclotrons use

International Nuclear Information System (INIS)

Araujo, Sumair G.

2002-01-01

Automation has a growing role in process controls in general. It is everyday more and present in human kind's dreams, being pursued by scientists as the solution to improve the quality of life, to replace big efforts, to attend the growing demand of the world populace. Automation is a technology that can be applied in several processes to generate productivity, agility, flexibility and welfare. It opens horizons so that man can multiply his potential, develop his creativity and gives birth to a new age of realizations. Where he will certainly will be the central figure, responsible for decisions. It is up to him to find the best way. In particular, automation of target irradiation systems in cyclotrons is important in order to reduce the radiation dose received by the personnel and to increase the reliability of the method, leading to an improvement in the radioisotope production capacity. This work presents a literature review of automatized systems comparing them with the one developed at IPEN. The systems found in literature involve the use of solid, liquid and gaseous targets used in radioisotope production for Nuclear Medicine employing the techniques of PET (Positron Emission Tomography) and SPET (Single Photon Emission Tomography). (author)

Automation and Intensity Modulated Radiation Therapy for Individualized High-Quality Tangent Breast Treatment Plans

International Nuclear Information System (INIS)

Purdie, Thomas G.; Dinniwell, Robert E.; Fyles, Anthony; Sharpe, Michael B.

2014-01-01

Purpose: To demonstrate the large-scale clinical implementation and performance of an automated treatment planning methodology for tangential breast intensity modulated radiation therapy (IMRT). Methods and Materials: Automated planning was used to prospectively plan tangential breast IMRT treatment for 1661 patients between June 2009 and November 2012. The automated planning method emulates the manual steps performed by the user during treatment planning, including anatomical segmentation, beam placement, optimization, dose calculation, and plan documentation. The user specifies clinical requirements of the plan to be generated through a user interface embedded in the planning system. The automated method uses heuristic algorithms to define and simplify the technical aspects of the treatment planning process. Results: Automated planning was used in 1661 of 1708 patients receiving tangential breast IMRT during the time interval studied. Therefore, automated planning was applicable in greater than 97% of cases. The time for treatment planning using the automated process is routinely 5 to 6 minutes on standard commercially available planning hardware. We have shown a consistent reduction in plan rejections from plan reviews through the standard quality control process or weekly quality review multidisciplinary breast rounds as we have automated the planning process for tangential breast IMRT. Clinical plan acceptance increased from 97.3% using our previous semiautomated inverse method to 98.9% using the fully automated method. Conclusions: Automation has become the routine standard method for treatment planning of tangential breast IMRT at our institution and is clinically feasible on a large scale. The method has wide clinical applicability and can add tremendous efficiency, standardization, and quality to the current treatment planning process. The use of automated methods can allow centers to more rapidly adopt IMRT and enhance access to the documented
Development of a fully automated software system for rapid analysis/processing of the falling weight deflectometer data.

Science.gov (United States)

2009-02-01

The Office of Special Investigations at Iowa Department of Transportation (DOT) collects FWD data on regular basis to evaluate pavement structural conditions. The primary objective of this study was to develop a fully-automated software system for ra...
Open-Source Automated Mapping Four-Point Probe

Directory of Open Access Journals (Sweden)

Handy Chandra

2017-01-01

Full Text Available Scientists have begun using self-replicating rapid prototyper (RepRap 3-D printers to manufacture open source digital designs of scientific equipment. This approach is refined here to develop a novel instrument capable of performing automated large-area four-point probe measurements. The designs for conversion of a RepRap 3-D printer to a 2-D open source four-point probe (OS4PP measurement device are detailed for the mechanical and electrical systems. Free and open source software and firmware are developed to operate the tool. The OS4PP was validated against a wide range of discrete resistors and indium tin oxide (ITO samples of different thicknesses both pre- and post-annealing. The OS4PP was then compared to two commercial proprietary systems. Results of resistors from 10 to 1 MΩ show errors of less than 1% for the OS4PP. The 3-D mapping of sheet resistance of ITO samples successfully demonstrated the automated capability to measure non-uniformities in large-area samples. The results indicate that all measured values are within the same order of magnitude when compared to two proprietary measurement systems. In conclusion, the OS4PP system, which costs less than 70% of manual proprietary systems, is comparable electrically while offering automated 100 micron positional accuracy for measuring sheet resistance over larger areas.
Open-Source Automated Mapping Four-Point Probe.

Science.gov (United States)

Chandra, Handy; Allen, Spencer W; Oberloier, Shane W; Bihari, Nupur; Gwamuri, Jephias; Pearce, Joshua M

2017-01-26

Scientists have begun using self-replicating rapid prototyper (RepRap) 3-D printers to manufacture open source digital designs of scientific equipment. This approach is refined here to develop a novel instrument capable of performing automated large-area four-point probe measurements. The designs for conversion of a RepRap 3-D printer to a 2-D open source four-point probe (OS4PP) measurement device are detailed for the mechanical and electrical systems. Free and open source software and firmware are developed to operate the tool. The OS4PP was validated against a wide range of discrete resistors and indium tin oxide (ITO) samples of different thicknesses both pre- and post-annealing. The OS4PP was then compared to two commercial proprietary systems. Results of resistors from 10 to 1 MΩ show errors of less than 1% for the OS4PP. The 3-D mapping of sheet resistance of ITO samples successfully demonstrated the automated capability to measure non-uniformities in large-area samples. The results indicate that all measured values are within the same order of magnitude when compared to two proprietary measurement systems. In conclusion, the OS4PP system, which costs less than 70% of manual proprietary systems, is comparable electrically while offering automated 100 micron positional accuracy for measuring sheet resistance over larger areas.
Classification of nuclear power plant operator support systems

International Nuclear Information System (INIS)

Alpeev, A.S.

1994-01-01

The objective of this survey was to examine the general characteristics of modern nuclear power plant process monitoring/control systems and to apply developing technology (intellectual automation) in order to improve the man-machine interface. The support systems that implement each phase of the control function...information, assessment, decision-making, and implementation...were discussed, and where applicable, intellectual automation was applied to the support system. It was concluded that the application of intellectual automation, as well as other (undefined) possibilities for improving the man-machine interface, would relieve the operator of many routine activities and allow him to readily apply high potential to those poorly-formalized scenarios in which the operator's work can't be automated. It was also concluded that the development of such support systems would not be without problems, i.e. software certification, traning, and jurisdictional questions
Mobile Techniques for Rapid Detection of Concealed Nuclear Material

International Nuclear Information System (INIS)

Rosenstock, W.; Koeble, T.; Risse, M.; Berky, W.

2015-01-01

To prevent the diversion of nuclear material as well as illicit production, transport and use of nuclear material we investigated in mobile techniques to detect and identify such material in the field as early as possible. For that purpose we use a highly sensitive gamma measurement system installed in a car. It consists of two large volume plastic scintillators, one on each side of the car, each scintillator with 12 l active volume, and two extreme sensitive high purity Germanium detectors with 57 cm 2 crystal diameter, cooled electrically. The measured data are processed immediately with integrated, appropriate analysis software for direct assessment including material identification and classification within seconds. The software for the plastic scintillators can differentiate between natural and artificial radioactivity, thus giving a clear hint for the existence of unexpected material. In addition, the system is equipped with highly sensitive neutron detectors. We have performed numerous measurements by passing different radioactive and nuclear sources in relatively large distances with this measurement car. Even shielded as well as masked material was detected and identified in most of the cases. We will report on the measurements performed in the field (on an exercise area) and in the lab and discuss the capabilities of the system, especially with respect to timeliness and identification. This system will improve the nuclear verification capabilities also. (author)
Broader utilization of programmable automation equipment in French nuclear power plants: Reflections on the choices made by Electricite de France and French designers

International Nuclear Information System (INIS)

Baudry, Y.; Varaldi, G.

1983-01-01

More than 1000 microprocessors and more than 10,000 data memories in each of the twenty or so 1300 MW units in the French nuclear programme: that was the decision taken by Electricite de France (EDF) in conjunction with the designers in 1974, with the intention of introducing programmable automata on a wide scale in French nuclear power plants. This programme was carried out with the assistance of advanced research services such as the universities, the Commissariat a l'energie atomique (CEA), EDF's design and research service and the designers, most of whom were already EDF suppliers for the 900 MW range. Having used computers for linking sequences (themselves carried out with electromagnetic technology) for its latest natural-uranium gas-cooled graphite-moderated power plants, EDF decided to call a temporary halt, in the case of its 900 MW light-water range, to the use of digital techniques for the control and automation of power plants although it continued to employ such techniques widely in data processing. Thus, the widespread introduction of programmable automata, which was decided upon in 1974/75 at a time when no equivalent existed at the international level, led EDF and French designers to undertake a major development effort in order to meet the requirements - particularly safety and reliability requirements - for such automata to be incorporated into the nuclear field. How does this choice fit in with the logical evolution of the digitalization of French nuclear power plants. What problems has it caused for EDF and French industry. How have these problems been tackled. How have they been overcome. These are the questions dealt with in this paper. (author)
Rapid Response Manufacturing (RRM). Final CRADA report

Energy Technology Data Exchange (ETDEWEB)

Cain, W.D. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States); Waddell, W.L. [National Centers for Manufacturing Sciences, Ann Arbor, MI (United States)

1997-08-28

A major accomplishment of the Rapid Response Manufacturing (RRM) project was the development of a broad-based generic framework for automating and integrating the design-to-manufacturing activities associated with machined part products. Key components of the framework are a manufacturing model that integrates product and process data in a consistent, minimally redundant manner, an advanced computer-aided engineering working environment, knowledge-based software systems for design, process planning, and manufacturing and new production technologies for making products directly from design application software.
Database automation of accelerator operation

International Nuclear Information System (INIS)

Casstevens, B.J.; Ludemann, C.A.

1983-01-01

Database management techniques are applied to automating the setup of operating parameters of a heavy-ion accelerator used in nuclear physics experiments. Data files consist of ion-beam attributes, the interconnection assignments of the numerous power supplies and magnetic elements that steer the ions' path through the system, the data values that represent the electrical currents supplied by the power supplies, as well as the positions of motors and status of mechanical actuators. The database is relational and permits searching on ranges of any subset of the ion-beam attributes. A file selected from the database is used by the control software to replicate the ion beam conditions by adjusting the physical elements in a continuous manner
Man and nuclear power plants

International Nuclear Information System (INIS)

Anon.

1978-01-01

According to the Inst. fuer Unfallforschung/TUeV Rheinland, Koeln, the interpretation of empirical data gained from the operation of nuclear power plants at home and abroad during the period 1967-1975 has shown that about 38% of all reactor accidents were caused by human failures. These occured either during the design and construction, the commissioning, the reconditioning or the operation of the plants. This very fact stresses human responsibility for the safety of nuclear power plants, in spite of those plants being automated to a high degree and devices. (orig.) [de
Nuclear energy data

International Nuclear Information System (INIS)

2004-01-01

This new edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, offers additional graphical information as compared with previous editions allowing a rapid comparison between capacity and requirements in the various phases of the nuclear fuel cycle. It provides the reader with a comprehensive but easy-to-access overview on the status of and trends in the nuclear power and fuel cycle sector. This publication is an authoritative information source of interest to policy makers, experts and academics involved in the nuclear energy field. (author)
The automated ground network system

Science.gov (United States)

Smith, Miles T.; Militch, Peter N.

1993-01-01

The primary goal of the Automated Ground Network System (AGNS) project is to reduce Ground Network (GN) station life-cycle costs. To accomplish this goal, the AGNS project will employ an object-oriented approach to develop a new infrastructure that will permit continuous application of new technologies and methodologies to the Ground Network's class of problems. The AGNS project is a Total Quality (TQ) project. Through use of an open collaborative development environment, developers and users will have equal input into the end-to-end design and development process. This will permit direct user input and feedback and will enable rapid prototyping for requirements clarification. This paper describes the AGNS objectives, operations concept, and proposed design.
MALDI-TOF mass spectrometry for rapid diagnosis of postoperative endophthalmitis.

Science.gov (United States)

Mailhac, Adriane; Durand, Harmonie; Boisset, Sandrine; Maubon, Danièle; Berger, Francois; Maurin, Max; Chiquet, Christophe; Bidart, Marie

2017-01-30

This study describes an innovative strategy for rapid detection and identification of bacteria causing endophthalmitis, combining the use of an automated blood culture system with MALDI-TOF mass spectrometry methodology. Using this protocol, we could identify 96% of 45 bacterial strains isolated from vitreous samples collected in acute post-operative endophthalmitis patients. Copyright © 2016 Elsevier B.V. All rights reserved.
Automated method of phasing difficult nuclear magnetic resonance spectra with application to the unsaturated carbon analysis of oils

Energy Technology Data Exchange (ETDEWEB)

Sterna, L.L.; Tong, V.P. (Shell Development Company, Houston, TX (USA). Westhollow Research Center)

1991-08-01

A new method for the automated phasing of n.m.r. spectra is described. The basis of the automation is that the software performs the phasing in the same fashion as a trained n.m.r. operator rather than using mathematical relationships between absorptive and dispersive spectra. The method is illustrated with processing of the {sup 13}C n.m.r. spectrum of a catalytic cracking feedstock. The software readily phased the spectrum even though the spectrum had very broad features and a significant baseline correction. The software performed well even when the time-domain data was left-shifted to introduce a large first-order phase error. The method was applied to measure the percentage of unsaturated carbon in hydrocarbons. Extensive tests were performed to compare automated processing with manual processing for this application; the automated method was found to give both better precision and accuracy. The method can be easily tailored to many other types of analyses. 9 refs., 4 figs., 3 tabs.
Development of a novel and automated fluorescent immunoassay for the analysis of beta-lactam antibiotics

NARCIS (Netherlands)

Benito-Pena, E.; Moreno-Bondi, M.C.; Orellana, G.; Maquieira, K.; Amerongen, van A.

2005-01-01

An automated immunosensor for the rapid and sensitive analysis of penicillin type -lactam antibiotics has been developed and optimized. An immunogen was prepared by coupling the common structure of the penicillanic -lactam antibiotics, i.e., 6-aminopenicillanic acid to keyhole limpet hemocyanin.
WALS: A sensor-based robotic system for handling nuclear materials

International Nuclear Information System (INIS)

Drotning, W.; Kimberly, H.; Wapman, W.

1997-01-01

An automated system is being developed for handling large payloads of radioactive nuclear materials in an analytical laboratory. The system uses machine vision and force/torque sensing to provide sensor-based control of the automation system to enhance system safety, flexibility, and robustness and achieve easy remote operation. The automation system also controls the operation of the laboratory measurement systems and the coordination of them with the robotic system. Particular attention has been given to system design features and analytical methods that provide an enhanced level of operational safety. Independent mechanical gripper interlock and too release mechanisms were designed to prevent payload mishandling. An extensive failure modes and effects analysis (FMEA) of the automation system was developed as a safety design analysis tool
ANA IIF Automation: Moving towards Harmonization? Results of a Multicenter Study

Directory of Open Access Journals (Sweden)

Stefanie Van den Bremt

2017-01-01

Full Text Available Background. Our study aimed to investigate whether the introduction of automated anti-nuclear antibody (ANA indirect immunofluorescence (IIF analysis decreases the interlaboratory variability of ANA titer results. Method. Three serum samples were sent to 10 laboratories using the QUANTA-Lyser® in combination with the NOVA View®. Each laboratory performed the ANA IIF analysis 10x in 1 run and 1x in 10 different runs and determined the endpoint titer by dilution. One of the three samples had been sent in 2012, before the era of ANA IIF automation, by the Belgian National External Quality Assessment (EQA Scheme. Harmonization was evaluated in terms of variability in fluorescence intensity (LIU and ANA IIF titer. Results. The evaluation of the intra- and interrun LIU variability revealed a larger variability for 2 laboratories, due to preanalytical and analytical problems. Reanalysis of the EQA sample resulted in a lower titer variability. Diluted endpoint titers were similar to the estimated single well titer and the overall median titer as reported by the EQA in 2012. Conclusion. The introduction of automated microscopic analysis allows more harmonized ANA IIF reporting, provided that this totally automated process is controlled by a thorough quality assurance program, covering the total ANA IIF process.
Role and position of Nuclear Power Plants Research Institute in nuclear power industry

International Nuclear Information System (INIS)

Metke, E.

1984-01-01

The Nuclear Power Plants Research Institute carries out applied and experimental research of the operating states of nuclear power plants, of new methods of surveillance and diagnosis of technical equipment, it prepares training of personnel, carries out tests, engineering and technical consultancy and the research of automated control systems. The main research programme of the Institute is the rationalization of raising the safety and operating reliability of WWER nuclear power plants. The Institute is also concerned with quality assurance of selected equipment of nuclear power plants and assembly works, with radioactive waste disposal and the decommissioning of nuclear power plants as well as with the preparation and implementation of the nuclear power plant start-up. The Research Institute is developing various types of equipment, such as equipment for the decontamination of the primary part of the steam generator, a continuous analyzer of chloride levels in water, a gas monitoring instrument, etc. The prospects are listed of the Research Institute and its cooperation with other CMEA member countries. (M.D.)
An Automated Detection System for Microaneurysms That Is Effective across Different Racial Groups

Directory of Open Access Journals (Sweden)

George Michael Saleh

2016-01-01

Full Text Available Patients without diabetic retinopathy (DR represent a large proportion of the caseload seen by the DR screening service so reliable recognition of the absence of DR in digital fundus images (DFIs is a prime focus of automated DR screening research. We investigate the use of a novel automated DR detection algorithm to assess retinal DFIs for absence of DR. A retrospective, masked, and controlled image-based study was undertaken. 17,850 DFIs of patients from six different countries were assessed for DR by the automated system and by human graders. The system’s performance was compared across DFIs from the different countries/racial groups. The sensitivities for detection of DR by the automated system were Kenya 92.8%, Botswana 90.1%, Norway 93.5%, Mongolia 91.3%, China 91.9%, and UK 90.1%. The specificities were Kenya 82.7%, Botswana 83.2%, Norway 81.3%, Mongolia 82.5%, China 83.0%, and UK 79%. There was little variability in the calculated sensitivities and specificities across the six different countries involved in the study. These data suggest the possible scalability of an automated DR detection platform that enables rapid identification of patients without DR across a wide range of races.
An automated procedure for identification of a person using gait analysis

Directory of Open Access Journals (Sweden)

Alena Galajdová

2016-10-01

Full Text Available Different biometric methods are available for identification purpose of a person. The most commonly used are fingerprints, but there are also other biometric methods such as voice, morphology of ears, structure of iris and so on. In some cases, it is required to identify a person according to his/her biomechanical parameters or even his/her gait pattern. Gait is an outstanding biometric behavioural characteristic that is not widely used yet for identification purposes because efficient and proven automated processes are not yet available. Several systems and gait pattern databases have been developed for rapid evaluation and processing of gait. This article describes an original automated evaluation procedure of gait pattern and identification of unique gait parameters for automatic identification purposes.

Lexical evolution rates derived from automated stability measures

Science.gov (United States)

Petroni, Filippo; Serva, Maurizio

2010-03-01

Phylogenetic trees can be reconstructed from the matrix which contains the distances between all pairs of languages in a family. Recently, we proposed a new method which uses normalized Levenshtein distances among words with the same meaning and averages over all the items of a given list. Decisions about the number of items in the input lists for language comparison have been debated since the beginning of glottochronology. The point is that words associated with some of the meanings have a rapid lexical evolution. Therefore, a large vocabulary comparison is only apparently more accurate than a smaller one, since many of the words do not carry any useful information. In principle, one should find the optimal length of the input lists, studying the stability of the different items. In this paper we tackle the problem with an automated methodology based only on our normalized Levenshtein distance. With this approach, the program of an automated reconstruction of language relationships is completed.
Technical study for the automation and control of processes of the chemical processing plant for liquid radioactive waste at Racso Nuclear Center

International Nuclear Information System (INIS)

Quevedo D, M.; Ayala S, A.

1997-01-01

The purpose of this study is to introduce the development of an automation and control system in a chemical processing plant for liquid radioactive waste of low and medium activity. The control system established for the chemical processing plant at RACSO Nuclear Center is described. It is an on-off sequential type system with feedback. This type of control has been chosen according to the volumes to be treated at the plant as processing is carried out by batches. The system will be governed by a programmable controller (PLC), modular, with a minimum of 24 digital inputs, 01 analog input, 16 digital outputs and 01 analog input. Digital inputs and outputs are specifically found at the level sensors of the tanks and at the solenoid-type electro valve control. Analog inputs and outputs have been considered at the pH control. The comprehensive system has been divided into three control bonds, The bonds considered for the operation of the plant are described, the plant has storing, fitting, processing and clarifying tanks. National Instruments' Lookout software has been used for simulation, constituting an important tool not only for a design phase but also for a practical one since this software will be used as SCADA system. Finally, the advantages and benefits of this automation system are analyzed, radiation doses received by occupationally exposed workers are reduced and reliability on the operation on the system is increased. (authors)
Lean automation development : applying lean principles to the automation development process

OpenAIRE

Granlund, Anna; Wiktorsson, Magnus; Grahn, Sten; Friedler, Niklas

2014-01-01

By a broad empirical study it is indicated that automation development show potential of improvement. In the paper, 13 lean product development principles are contrasted to the automation development process and it is suggested why and how these principles can facilitate, support and improve the automation development process. The paper summarises a description of what characterises a lean automation development process and what consequences it entails. Main differences compared to current pr...
Automated gamma spectrometry and data analysis on radiometric neutron dosimeters

International Nuclear Information System (INIS)

Matsumoto, W.Y.

1983-01-01

An automated gamma-ray spectrometry system was designed and implemented by the Westinghouse Hanford Company at the Hanford Engineering Development Laboratory (HEDL) to analyze radiometric neutron dosimeters. Unattended, automatic, 24 hour/day, 7 day/week operation with online data analysis and mainframe-computer compatible magnetic tape output are system features. The system was used to analyze most of the 4000-plus radiometric monitors (RM's) from extensive reactor characterization tests during startup and initial operation of th Fast Flux Test Facility (FFTF). The FFTF, operated by HEDL for the Department of Energy, incorporates a 400 MW(th) sodium-cooled fast reactor. Aumomated system hardware consists of a high purity germanium detector, a computerized multichannel analyzer data acquisition system (Nuclear Data, Inc. Model 6620) with two dual 2.5 Mbyte magnetic disk drives plus two 10.5 inch reel magnetic tape units for mass storage of programs/data and an automated Sample Changer-Positioner (ASC-P) run with a programmable controller. The ASC-P has a 200 sample capacity and 12 calibrated counting (analysis) positions ranging from 6 inches (15 cm) to more than 20 feet (6.1 m) from the detector. The system software was programmed in Fortran at HEDL, except for the Nuclear Data, Inc. Peak Search and Analysis Program and Disk Operating System (MIDAS+)
What Discrete and Serial Rapid Automatized Naming Can Reveal about Reading

Science.gov (United States)

de Jong, Peter F.

2011-01-01

Serial rapid automized naming (RAN) has been often found to correlate more strongly with reading than discrete RAN. This study aimed to demonstrate that the strength of the RAN-reading fluency relationship is dependent on the format of both RAN and the reading task if the reading task consists of sight words. Seventy-one first-grade, 74…
Automation system for operation of nuclear power plant

International Nuclear Information System (INIS)

Kinoshita, Mitsuo; Fukuzaki, Koji; Kato, Kanji

1991-01-01

The automation system comprises a general monitor control device incorporating a plurality of emergency operation plannings concerning an automatic processing, and judging whether the operation is to be conducted or not depending on the plannings based on the data planed by a plant, a control device for controlling the plant in accordance with the planning when monitor control device judges that the operation should be done due to the emergency operation plannings and an operation planning device aiding the formation of the operation plannings. When the state of the power plant exceeds a normal control region, the reactor power is lowered automatically by so much as a predetermined value or to a predetermined level, to automatically return the plant state to the normal control region. In this way, the plant operation efficiency can be improved. Further, after automatic operation, since operation plannings for recovering original operation plannings are prepared efficiently and recovered operation plannings are started in a short period of time, the operators' burden can be mitigated and power saving can be attained. (N.H.)
Rapid automated superposition of shapes and macromolecular models using spherical harmonics.

Science.gov (United States)

Konarev, Petr V; Petoukhov, Maxim V; Svergun, Dmitri I

2016-06-01

A rapid algorithm to superimpose macromolecular models in Fourier space is proposed and implemented ( SUPALM ). The method uses a normalized integrated cross-term of the scattering amplitudes as a proximity measure between two three-dimensional objects. The reciprocal-space algorithm allows for direct matching of heterogeneous objects including high- and low-resolution models represented by atomic coordinates, beads or dummy residue chains as well as electron microscopy density maps and inhomogeneous multi-phase models ( e.g. of protein-nucleic acid complexes). Using spherical harmonics for the computation of the amplitudes, the method is up to an order of magnitude faster than the real-space algorithm implemented in SUPCOMB by Kozin & Svergun [ J. Appl. Cryst. (2001 ▸), 34 , 33-41]. The utility of the new method is demonstrated in a number of test cases and compared with the results of SUPCOMB . The spherical harmonics algorithm is best suited for low-resolution shape models, e.g . those provided by solution scattering experiments, but also facilitates a rapid cross-validation against structural models obtained by other methods.
Centrality, Rapidity And Transverse-Momentum Dependence of Cold Nuclear Matter Effects on J/Psi Production in D Au, Cu Cu And Au Au Collisions at S(NN)**(1/2)

Energy Technology Data Exchange (ETDEWEB)

Ferreiro, E.G.; /Santiago de Compostela U.; Fleuret, F.; /Ecole Polytechnique; Lansberg, J.P.; /Ecole Polytechnique /SLAC; Rakotozafindrabe, A.; /SPhN, DAPNIA, Saclay

2011-11-11

We have carried out a wide study of Cold Nuclear Matter (CNM) effects on J/{Psi} = production in dAu, CuCu and AuAu collisions at {radical}s{sub NN} = 200 GeV. We have studied the effects of three different gluon-shadowing parameterizations, using the usual simplified kinematics for which the momentum of the gluon recoiling against the J/{Psi} is neglected as well as an exact kinematics for a 2 {yields} 2 process, namely g + g {yields} J/{psi} + g as expected from LO pQCD. We have shown that the rapidity distribution of the nuclear modification factor R{sub dAu}, and particularly its anti-shadowing peak, is systematically shifted toward larger rapidities in the 2 {yields} 2 kinematics, irrespective of which shadowing parameterization is used. In turn, we have noted differences in the effective final-state nuclear absorption needed to fit the PHENIX dAu data. Taking advantage of our implementation of a 2 {yields} 2 kinematics, we have also computed the transverse momentum dependence of the nuclear modification factor, which cannot be predicted with the usual simplified kinematics. All the corresponding observables have been computed for CuCu and AuAu collisions and compared to the PHENIX and STAR data. Finally, we have extracted the effective nuclear absorption from the recent measurements of RCP in dAu collisions by the PHENIX collaboration.
Both Automation and Paper.

Science.gov (United States)

Purcell, Royal

1988-01-01

Discusses the concept of a paperless society and the current situation in library automation. Various applications of automation and telecommunications are addressed, and future library automation is considered. Automation at the Monroe County Public Library in Bloomington, Indiana, is described as an example. (MES)
Automated numerical simulation of cracked plates, pipes and elbows

International Nuclear Information System (INIS)

Reddy, Babu; Sreehari Kumar, B.; Bhate, S.R.; Kushwaha, H.S.

2008-01-01

In the nuclear industry, piping components are one of the key elements participating in its operation. Integrity of structural tubes and pipes plays a major role in nuclear power plants. The ideal procedure to ensure this aspect would be to conduct experimental studies on pilot/test specimens. However, it may not always be feasible to carry out the experimental investigation, as it requires pre-requisite infrastructure which may not be economically viable. This makes it imperative to conduct numerical simulations of the same particularly in the study of presence of cracks in the critical components. While performing the effect of cracks, the quality of the finite element mesh nearer to the crack tip plays a critical role while estimating J-integral value. The designer is often familiar with design methodology only and he obviously requires a convenient and reliable numerical tool to model and perform the analysis. In this context, an effort has been made in NISA, the general purpose finite element software, to automate the generation of FE meshes for a set of pre-defined components with different crack configurations. To simplify the procedure of FE mesh generation, analysis, and post processing, a graphical user interface (GUI) has been developed accordingly. This paper discusses the automated numerical simulation of plates and pipes with different crack configurations. This simulation software is also designed to help parametric study of cracked pipes. (author)
Intelligent distributed control for nuclear power plants

International Nuclear Information System (INIS)

Klevans, E.H.; Edwards, R.M.; Ray, A.; Lee, K.Y.; Garcia, H.E.: Chavez, C.M.; Turso, J.A.; BenAbdennour, A.

1991-01-01

In September of 1989 work began on the DOE University Program grant DE-FG07-89ER12889. The grant provides support for a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Second Annual Technical Progress report covers the period from September 1990 to September 1991. It summarizes the second year accomplishments while the appendices provide detailed information presented at conference meetings. These are two primary goals of this research. The first is to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz, a project consultant during the first year of the project. This philosophy, as presented in the first annual technical progress report, is to improve public perception of the safety of nuclear power plants by incorporating a high degree automation where greatly simplified operator control console minimizes the possibility of human error in power plant operations. A hierarchically distributed control system with automated responses to plant upset conditions is the focus of our research to achieve this goal. The second goal is to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-II steam plant
Moving toward the automation of the systematic review process: a summary of discussions at the second meeting of International Collaboration for the Automation of Systematic Reviews (ICASR).

Science.gov (United States)

O'Connor, Annette M; Tsafnat, Guy; Gilbert, Stephen B; Thayer, Kristina A; Wolfe, Mary S

2018-01-09

The second meeting of the International Collaboration for Automation of Systematic Reviews (ICASR) was held 3-4 October 2016 in Philadelphia, Pennsylvania, USA. ICASR is an interdisciplinary group whose aim is to maximize the use of technology for conducting rapid, accurate, and efficient systematic reviews of scientific evidence. Having automated tools for systematic review should enable more transparent and timely review, maximizing the potential for identifying and translating research findings to practical application. The meeting brought together multiple stakeholder groups including users of summarized research, methodologists who explore production processes and systematic review quality, and technologists such as software developers, statisticians, and vendors. This diversity of participants was intended to ensure effective communication with numerous stakeholders about progress toward automation of systematic reviews and stimulate discussion about potential solutions to identified challenges. The meeting highlighted challenges, both simple and complex, and raised awareness among participants about ongoing efforts by various stakeholders. An outcome of this forum was to identify several short-term projects that participants felt would advance the automation of tasks in the systematic review workflow including (1) fostering better understanding about available tools, (2) developing validated datasets for testing new tools, (3) determining a standard method to facilitate interoperability of tools such as through an application programming interface or API, and (4) establishing criteria to evaluate the quality of tools' output. ICASR 2016 provided a beneficial forum to foster focused discussion about tool development and resources and reconfirm ICASR members' commitment toward systematic reviews' automation.
Comparison radiographic and automated ultrasonic inspection of pipeline tie-in welds

International Nuclear Information System (INIS)

Connelly, T.; Gross, B.

2007-01-01

In recent years the use of automated ultrasonic inspection (AUT) for pipeline girth welds has seen rapid growth and is now used almost exclusively for all gas metal arc welding (GMAW) girth weld inspection. The following paper reviews some of the major features of ultrasonic inspection by comparison to conventional Film Radiography (RT) and reviews the use of ultrasonic inspection for pipeline and tie-in welds. (author)
Knowledge Management Seminar on Nuclear Sector at UPM, an initiative of the IAEA; Seminario de Gestion del Conocimiento en el Sector Nuclear en la UPM, una iniciativa de la IAEA

Energy Technology Data Exchange (ETDEWEB)

Jimenez, G.; Minguez, E.; Sbaffoni, M.

2012-07-01

Nuclear technology, developed over fifty years of knowledge, comprises many disciplines such as mechanical engineering, nuclear physics, automation, etc. During the operational experience of current reactors has developed a great knowledge that needs to be managed properly so present and future generations can enjoy this technology.
Rapidly Adaptable Instrumentation Tester (RAIT)

International Nuclear Information System (INIS)

Vargo, Timothy D.

1999-01-01

Emerging technologies in the field of ''Test ampersand Measurement'' have recently enabled the development of the Rapidly Adaptable Instrumentation Tester (RAIT). Based on software developed with LabVIEW, the RAIT design enables quick reconfiguration to test and calibrate a wide variety of telemetry systems. The consequences of inadequate testing could be devastating if a telemetry system were to fail during an expensive flight mission. Supporting both open-bench testing as well as automated test sequences, the RAIT has significantly lowered total time required to test and calibrate a system. This has resulted in an overall lower per unit testing cost than has been achievable in the past
Automated Groundwater Screening

International Nuclear Information System (INIS)

Taylor, Glenn A.; Collard, Leonard B.

2005-01-01

The Automated Intruder Analysis has been extended to include an Automated Ground Water Screening option. This option screens 825 radionuclides while rigorously applying the National Council on Radiation Protection (NCRP) methodology. An extension to that methodology is presented to give a more realistic screening factor for those radionuclides which have significant daughters. The extension has the promise of reducing the number of radionuclides which must be tracked by the customer. By combining the Automated Intruder Analysis with the Automated Groundwater Screening a consistent set of assumptions and databases is used. A method is proposed to eliminate trigger values by performing rigorous calculation of the screening factor thereby reducing the number of radionuclides sent to further analysis. Using the same problem definitions as in previous groundwater screenings, the automated groundwater screening found one additional nuclide, Ge-68, which failed the screening. It also found that 18 of the 57 radionuclides contained in NCRP Table 3.1 failed the screening. This report describes the automated groundwater screening computer application
PONDEROSA-C/S: client-server based software package for automated protein 3D structure determination.

Science.gov (United States)

Lee, Woonghee; Stark, Jaime L; Markley, John L

2014-11-01

Peak-picking Of Noe Data Enabled by Restriction Of Shift Assignments-Client Server (PONDEROSA-C/S) builds on the original PONDEROSA software (Lee et al. in Bioinformatics 27:1727-1728. doi: 10.1093/bioinformatics/btr200, 2011) and includes improved features for structure calculation and refinement. PONDEROSA-C/S consists of three programs: Ponderosa Server, Ponderosa Client, and Ponderosa Analyzer. PONDEROSA-C/S takes as input the protein sequence, a list of assigned chemical shifts, and nuclear Overhauser data sets ((13)C- and/or (15)N-NOESY). The output is a set of assigned NOEs and 3D structural models for the protein. Ponderosa Analyzer supports the visualization, validation, and refinement of the results from Ponderosa Server. These tools enable semi-automated NMR-based structure determination of proteins in a rapid and robust fashion. We present examples showing the use of PONDEROSA-C/S in solving structures of four proteins: two that enable comparison with the original PONDEROSA package, and two from the Critical Assessment of automated Structure Determination by NMR (Rosato et al. in Nat Methods 6:625-626. doi: 10.1038/nmeth0909-625 , 2009) competition. The software package can be downloaded freely in binary format from http://pine.nmrfam.wisc.edu/download_packages.html. Registered users of the National Magnetic Resonance Facility at Madison can submit jobs to the PONDEROSA-C/S server at http://ponderosa.nmrfam.wisc.edu, where instructions, tutorials, and instructions can be found. Structures are normally returned within 1-2 days.
Rapid quantification of viable Legionella in nuclear cooling tower waters using filter cultivation, fluorescent in situ hybridization and solid-phase cytometry.

Science.gov (United States)

Baudart, J; Guillaume, C; Mercier, A; Lebaron, P; Binet, M

2015-05-01

To develop a rapid and sensitive method to quantify viable Legionella spp. in cooling tower water samples. A rapid, culture-based method capable of quantifying as few as 600 Legionella microcolonies per litre within 2 days in industrial waters was developed. The method combines a short cultivation step of microcolonies on GVPC agar plate, specific detection of Legionella cells by a fluorescent in situ hybridization (FISH) approach, and a sensitive enumeration using a solid-phase cytometer. Following optimization of the cultivation conditions, the qualitative and quantitative performance of the method was assessed and the method was applied to 262 nuclear power plant cooling water samples. The performance of this method was in accordance with the culture method (NF-T 90-431) for Legionella enumeration. The rapid detection of viable Legionella in water is a major concern to the effective monitoring of this pathogenic bacterium in the main water sources involved in the transmission of legionellosis infection (Legionnaires' disease). The new method proposed here appears to be a robust, efficient and innovative means for rapidly quantifying cultivable Legionella in cooling tower water samples within 48 h. © 2015 The Society for Applied Microbiology.
INFORMATION SYSTEM OF AUTOMATION OF PREPARATION EDUCATIONAL PROCESS DOCUMENTS

Directory of Open Access Journals (Sweden)

V. A. Matyushenko

2016-01-01

Full Text Available Information technology is rapidly conquering the world, permeating all spheres of human activity. Education is not an exception. An important direction of information of education is the development of university management systems. Modern information systems improve and facilitate the management of all types of activities of the institution. The purpose of this paper is development of system, which allows automating process of formation of accounting documents. The article describes the problem of preparation of the educational process documents. Decided to project and create the information system in Microsoft Access environment. The result is four types of reports obtained by using the developed system. The use of this system now allows you to automate the process and reduce the effort required to prepare accounting documents. All reports was implement in Microsoft Excel software product and can be used for further analysis and processing.
Prototype for an automated technical specification information system

International Nuclear Information System (INIS)

Quinn, E.L.; Mills, R.H.; Groves, J.E.

1985-01-01

The Southern California Edison (SCE) Automated Technical Specification Information System (ATSIS) at the San Onofre nuclear generating station (SONGS) has been developed as a prototype for an on-line information management system. This system provides an appropriate level of update, inquiry, and report generation capabilities to help support plant operators at SONGS in their efforts to anticipate, identify, document, and track certain actions and activities associated with plant technical specifications and associated limiting conditions of operation (LCOs). Substantially increased emphasis is being placed on adherence to nuclear regulatory requirements and commitments contained on the operating licenses of nuclear power plants. Additionally, as each year passes, such requirements are becoming increasingly detailed and complex, making it more and more difficult to track and ensure total compliance with the many and varied requirements. To assist the operations department at SONGs in meeting their regulatory commitments, in January 1985 SCE commenced gathering together the leading technical expertise available in the industry to develop a computerized system to track all technical specification-related equipment for operability and impact on LCOs

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