Methods and apparatus for capture and storage of semantic information with sub-files in a parallel computing system

Science.gov (United States)

Faibish, Sorin; Bent, John M; Tzelnic, Percy; Grider, Gary; Torres, Aaron

2015-02-03

Techniques are provided for storing files in a parallel computing system using sub-files with semantically meaningful boundaries. A method is provided for storing at least one file generated by a distributed application in a parallel computing system. The file comprises one or more of a complete file and a plurality of sub-files. The method comprises the steps of obtaining a user specification of semantic information related to the file; providing the semantic information as a data structure description to a data formatting library write function; and storing the semantic information related to the file with one or more of the sub-files in one or more storage nodes of the parallel computing system. The semantic information provides a description of data in the file. The sub-files can be replicated based on semantically meaningful boundaries.

The image database management system of teaching file using personal computer

International Nuclear Information System (INIS)

Shin, M. J.; Kim, G. W.; Chun, T. J.; Ahn, W. H.; Baik, S. K.; Choi, H. Y.; Kim, B. G.

1995-01-01

For the systemic management and easy using of teaching file in radiology department, the authors tried to do the setup of a database management system of teaching file using personal computer. We used a personal computer (IBM PC compatible, 486DX2) including a image capture card(Window vision, Dooin Elect, Seoul, Korea) and video camera recorder (8mm, CCD-TR105, Sony, Tokyo, Japan) for the acquisition and storage of images. We developed the database program by using Foxpro for Window 2.6(Microsoft, Seattle, USA) executed in the Window 3.1 (Microsoft, Seattle, USA). Each datum consisted of hospital number, name, sex, age, examination date, keyword, radiologic examination modalities, final diagnosis, radiologic findings, references and representative images. The images were acquired and stored as bitmap format (8 bitmap, 540 X 390 ∼ 545 X 414, 256 gray scale) and displayed on the 17 inch-flat monitor(1024 X 768, Samtron, Seoul, Korea). Without special devices, the images acquisition and storage could be done on the reading viewbox, simply. The image quality on the computer's monitor was less than the one of original film on the viewbox, but generally the characteristics of each lesions could be differentiated. Easy retrieval of data was possible for the purpose of teaching file system. Without high cost appliances, we could consummate the image database system of teaching file using personal computer with relatively inexpensive method

Processing of evaluated neutron data files in ENDF format on personal computers

International Nuclear Information System (INIS)

Vertes, P.

1991-11-01

A computer code package - FDMXPC - has been developed for processing evaluated data files in ENDF format. The earlier version of this package is supplemented with modules performing calculations using Reich-Moore and Adler-Adler resonance parameters. The processing of evaluated neutron data files by personal computers requires special programming considerations outlined in this report. The scope of the FDMXPC program system is demonstrated by means of numerical examples. (author). 5 refs, 4 figs, 4 tabs

Computer aided safety analysis 1989

International Nuclear Information System (INIS)

1990-04-01

The meeting was conducted in a workshop style, to encourage involvement of all participants during the discussions. Forty-five (45) experts from 19 countries, plus 22 experts from the GDR participated in the meeting. A list of participants can be found at the end of this volume. Forty-two (42) papers were presented and discussed during the meeting. Additionally an open discussion was held on the possible directions of the IAEA programme on Computer Aided Safety Analysis. A summary of the conclusions of these discussions is presented in the publication. The remainder of this proceedings volume comprises the transcript of selected technical papers (22) presented in the meeting. It is the intention of the IAEA that the publication of these proceedings will extend the benefits of the discussions held during the meeting to a larger audience throughout the world. The Technical Committee/Workshop on Computer Aided Safety Analysis was organized by the IAEA in cooperation with the National Board for Safety and Radiological Protection (SAAS) of the German Democratic Republic in Berlin. The purpose of the meeting was to provide an opportunity for discussions on experiences in the use of computer codes used for safety analysis of nuclear power plants. In particular it was intended to provide a forum for exchange of information among experts using computer codes for safety analysis under the Technical Cooperation Programme on Safety of WWER Type Reactors (RER/9/004) and other experts throughout the world. A separate abstract was prepared for each of the 22 selected papers. Refs, figs tabs and pictures

Survey on Security Issues in File Management in Cloud Computing Environment

Science.gov (United States)

Gupta, Udit

2015-06-01

Cloud computing has pervaded through every aspect of Information technology in past decade. It has become easier to process plethora of data, generated by various devices in real time, with the advent of cloud networks. The privacy of users data is maintained by data centers around the world and hence it has become feasible to operate on that data from lightweight portable devices. But with ease of processing comes the security aspect of the data. One such security aspect is secure file transfer either internally within cloud or externally from one cloud network to another. File management is central to cloud computing and it is paramount to address the security concerns which arise out of it. This survey paper aims to elucidate the various protocols which can be used for secure file transfer and analyze the ramifications of using each protocol.

Informatics in Radiology (infoRAD): personal computer security: part 2. Software Configuration and file protection.

Science.gov (United States)

Caruso, Ronald D

2004-01-01

Proper configuration of software security settings and proper file management are necessary and important elements of safe computer use. Unfortunately, the configuration of software security options is often not user friendly. Safe file management requires the use of several utilities, most of which are already installed on the computer or available as freeware. Among these file operations are setting passwords, defragmentation, deletion, wiping, removal of personal information, and encryption. For example, Digital Imaging and Communications in Medicine medical images need to be anonymized, or "scrubbed," to remove patient identifying information in the header section prior to their use in a public educational or research environment. The choices made with respect to computer security may affect the convenience of the computing process. Ultimately, the degree of inconvenience accepted will depend on the sensitivity of the files and communications to be protected and the tolerance of the user. Copyright RSNA, 2004

A technique for integrating remote minicomputers into a general computer's file system

CERN Document Server

Russell, R D

1976-01-01

This paper describes a simple technique for interfacing remote minicomputers used for real-time data acquisition into the file system of a central computer. Developed as part of the ORION system at CERN, this 'File Manager' subsystem enables a program in the minicomputer to access and manipulate files of any type as if they resided on a storage device attached to the minicomputer. Yet, completely transparent to the program, the files are accessed from disks on the central system via high-speed data links, with response times comparable to local storage devices. (6 refs).

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-06-20

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

International Nuclear Information System (INIS)

1994-01-01

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

A software to report and file by personal computer

International Nuclear Information System (INIS)

Di Giandomenico, E.; Filippone, A.; Esposito, A.; Bonomo, L.

1989-01-01

During the past four years the authors have been gaining experince in reporting radiological examinations by personal computer. Today they describe the project of a new software which allows the reporting and filing of roentgenograms. This program was realized by a radiologist, using a well known data base management system: dBASE III. The program was shaped to fit the radiologist's needs: it helps to report, and allows to file, radiological data, with the diagnosic codes used by the American College of Radiology. In this paper the authors describe the data base structure and indicate the software functions which make its use possible. Thus, this paper is not aimed at advertising a new reporting program, but at demonstrating how the radiologist can himself manage some aspects of his work with the help of a personal computer

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

Anatomy of safety-critical computing problems

International Nuclear Information System (INIS)

Swu Yih; Fan Chinfeng; Shirazi, Behrooz

1995-01-01

This paper analyzes the obstacles faced by current safety-critical computing applications. The major problem lies in the difficulty to provide complete and convincing safety evidence to prove that the software is safe. We explain this problem from a fundamental perspective by analyzing the essence of safety analysis against that of software developed by current practice. Our basic belief is that in order to perform a successful safety analysis, the state space structure of the analyzed system must have some properties as prerequisites. We propose the concept of safety analyzability, and derive its necessary and sufficient conditions; namely, definability, finiteness, commensurability, and tractability. We then examine software state space structures against these conditions, and affirm that the safety analyzability of safety-critical software developed by current practice is severely restricted by its state space structure and by the problem of exponential growth cost. Thus, except for small and simple systems, the safety evidence may not be complete and convincing. Our concepts and arguments successfully explain the current problematic situation faced by the safety-critical computing domain. The implications are also discussed

Software Safety Risk in Legacy Safety-Critical Computer Systems

Science.gov (United States)

Hill, Janice L.; Baggs, Rhoda

2007-01-01

Safety Standards contain technical and process-oriented safety requirements. Technical requirements are those such as "must work" and "must not work" functions in the system. Process-Oriented requirements are software engineering and safety management process requirements. Address the system perspective and some cover just software in the system > NASA-STD-8719.13B Software Safety Standard is the current standard of interest. NASA programs/projects will have their own set of safety requirements derived from the standard. Safety Cases: a) Documented demonstration that a system complies with the specified safety requirements. b) Evidence is gathered on the integrity of the system and put forward as an argued case. [Gardener (ed.)] c) Problems occur when trying to meet safety standards, and thus make retrospective safety cases, in legacy safety-critical computer systems.

Comparison of canal transportation and centering ability of hand Protaper files and rotary Protaper files by using micro computed tomography

OpenAIRE

Amit Gandhi; Taru Gandhi

2011-01-01

Introduction and objective: The aim of the present study was to compare root canal preparation with rotary ProTaper files and hand ProTaper files to find a better instrumentation technique for maintaining root canal geometry with the aid of computed tomography. Material and methods: Twenty curved root canals with at least 10 degree of curvature were divided into 2 groups of 10 teeth each. In group I the canals were prepared with hand ProTaper files and in group II the canals were prepared wit...

Regulatory considerations for computational requirements for nuclear criticality safety

International Nuclear Information System (INIS)

Bidinger, G.H.

1995-01-01

As part of its safety mission, the U.S. Nuclear Regulatory Commission (NRC) approves the use of computational methods as part of the demonstration of nuclear criticality safety. While each NRC office has different criteria for accepting computational methods for nuclear criticality safety results, the Office of Nuclear Materials Safety and Safeguards (NMSS) approves the use of specific computational methods and methodologies for nuclear criticality safety analyses by specific companies (licensees or consultants). By contrast, the Office of Nuclear Reactor Regulation approves codes for general use. Historically, computational methods progressed from empirical methods to one-dimensional diffusion and discrete ordinates transport calculations and then to three-dimensional Monte Carlo transport calculations. With the advent of faster computational ability, three-dimensional diffusion and discrete ordinates transport calculations are gaining favor. With the proper user controls, NMSS has accepted any and all of these methods for demonstrations of nuclear criticality safety

Industrial Personal Computer based Display for Nuclear Safety System

International Nuclear Information System (INIS)

Kim, Ji Hyeon; Kim, Aram; Jo, Jung Hee; Kim, Ki Beom; Cheon, Sung Hyun; Cho, Joo Hyun; Sohn, Se Do; Baek, Seung Min

2014-01-01

The safety display of nuclear system has been classified as important to safety (SIL:Safety Integrity Level 3). These days the regulatory agencies are imposing more strict safety requirements for digital safety display system. To satisfy these requirements, it is necessary to develop a safety-critical (SIL 4) grade safety display system. This paper proposes industrial personal computer based safety display system with safety grade operating system and safety grade display methods. The description consists of three parts, the background, the safety requirements and the proposed safety display system design. The hardware platform is designed using commercially available off-the-shelf processor board with back plane bus. The operating system is customized for nuclear safety display application. The display unit is designed adopting two improvement features, i.e., one is to provide two separate processors for main computer and display device using serial communication, and the other is to use Digital Visual Interface between main computer and display device. In this case the main computer uses minimized graphic functions for safety display. The display design is at the conceptual phase, and there are several open areas to be concreted for a solid system. The main purpose of this paper is to describe and suggest a methodology to develop a safety-critical display system and the descriptions are focused on the safety requirement point of view

Industrial Personal Computer based Display for Nuclear Safety System

Energy Technology Data Exchange (ETDEWEB)

Kim, Ji Hyeon; Kim, Aram; Jo, Jung Hee; Kim, Ki Beom; Cheon, Sung Hyun; Cho, Joo Hyun; Sohn, Se Do; Baek, Seung Min [KEPCO, Youngin (Korea, Republic of)

2014-08-15

The safety display of nuclear system has been classified as important to safety (SIL:Safety Integrity Level 3). These days the regulatory agencies are imposing more strict safety requirements for digital safety display system. To satisfy these requirements, it is necessary to develop a safety-critical (SIL 4) grade safety display system. This paper proposes industrial personal computer based safety display system with safety grade operating system and safety grade display methods. The description consists of three parts, the background, the safety requirements and the proposed safety display system design. The hardware platform is designed using commercially available off-the-shelf processor board with back plane bus. The operating system is customized for nuclear safety display application. The display unit is designed adopting two improvement features, i.e., one is to provide two separate processors for main computer and display device using serial communication, and the other is to use Digital Visual Interface between main computer and display device. In this case the main computer uses minimized graphic functions for safety display. The display design is at the conceptual phase, and there are several open areas to be concreted for a solid system. The main purpose of this paper is to describe and suggest a methodology to develop a safety-critical display system and the descriptions are focused on the safety requirement point of view.

A Methodological Framework for Software Safety in Safety Critical Computer Systems

OpenAIRE

P. V. Srinivas Acharyulu; P. Seetharamaiah

2012-01-01

Software safety must deal with the principles of safety management, safety engineering and software engineering for developing safety-critical computer systems, with the target of making the system safe, risk-free and fail-safe in addition to provide a clarified differentaition for assessing and evaluating the risk, with the principles of software risk management. Problem statement: Prevailing software quality models, standards were not subsisting in adequately addressing the software safety ...

[Comparison of effectiveness and safety between Twisted File technique and ProTaper Universal rotary full sequence based on micro-computed tomography].

Science.gov (United States)

Chen, Xiao-bo; Chen, Chen; Liang, Yu-hong

2016-02-18

To evaluate the efficacy and security of two type of rotary nickel titanium system (Twisted File and ProTaper Universal) for root canal preparation based on micro-computed tomography(micro-CT). Twenty extracted molars (including 62 canals) were divided into two experimental groups and were respectively instrumented using Twisted File rotary nickel titanium system (TF) and ProTaper Universal rotary nickel titanium system (PU) to #25/0.08 following recommended protocol. Time for root canal instrumentation (accumulation of time for every single file) was recorded. The 0-3 mm root surface from apex was observed under an optical stereomicroscope at 25 × magnification. The presence of crack line was noted. The root canals were scanned with micro-CT before and after root canal preparation. Three-dimensional shape images of canals were reconstructed, calculated and evaluated. The amount of canal central transportation of the two groups was calculated and compared. The shorter preparation time [(0.53 ± 0.14) min] was observed in TF group, while the preparation time of PU group was (2.06 ± 0.39) min (Pvs. (0.097 ± 0.084) mm, P<0.05]. No instrument separation was observed in both the groups. Cracks were not found in both the groups either based in micro-CT images or observation under an optical stereomicroscope at 25 × magnification. Compared with ProTaper Universal, Twisted File took less time in root canal preparation and exhibited better shaping ability, and less canal transportation.

Cooperative storage of shared files in a parallel computing system with dynamic block size

Science.gov (United States)

Bent, John M.; Faibish, Sorin; Grider, Gary

2015-11-10

Improved techniques are provided for parallel writing of data to a shared object in a parallel computing system. A method is provided for storing data generated by a plurality of parallel processes to a shared object in a parallel computing system. The method is performed by at least one of the processes and comprises: dynamically determining a block size for storing the data; exchanging a determined amount of the data with at least one additional process to achieve a block of the data having the dynamically determined block size; and writing the block of the data having the dynamically determined block size to a file system. The determined block size comprises, e.g., a total amount of the data to be stored divided by the number of parallel processes. The file system comprises, for example, a log structured virtual parallel file system, such as a Parallel Log-Structured File System (PLFS).

Computer codes for safety analysis

International Nuclear Information System (INIS)

Holland, D.F.

1986-11-01

Computer codes for fusion safety analysis have been under development in the United States for about a decade. This paper will discuss five codes that are currently under development by the Fusion Safety Program. The purpose and capability of each code will be presented, a sample given, followed by a discussion of the present status and future development plans

49 CFR 564.5 - Information filing; agency processing of filings.

Science.gov (United States)

2010-10-01

... 49 Transportation 6 2010-10-01 2010-10-01 false Information filing; agency processing of filings... HIGHWAY TRAFFIC SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REPLACEABLE LIGHT SOURCE INFORMATION (Eff. until 12-01-12) § 564.5 Information filing; agency processing of filings. (a) Each manufacturer...

Safety analysis of control rod drive computers

International Nuclear Information System (INIS)

Ehrenberger, W.; Rauch, G.; Schmeil, U.; Maertz, J.; Mainka, E.U.; Nordland, O.; Gloee, G.

1985-01-01

The analysis of the most significant user programmes revealed no errors in these programmes. The evaluation of approximately 82 cumulated years of operation demonstrated that the operating system of the control rod positioning processor has a reliability that is sufficiently good for the tasks this computer has to fulfil. Computers can be used for safety relevant tasks. The experience gained with the control rod positioning processor confirms that computers are not less reliable than conventional instrumentation and control system for comparable tasks. The examination and evaluation of computers for safety relevant tasks can be done with programme analysis or statistical evaluation of the operating experience. Programme analysis is recommended for seldom used and well structured programmes. For programmes with a long, cumulated operating time a statistical evaluation is more advisable. The effort for examination and evaluation is not greater than the corresponding effort for conventional instrumentation and control systems. This project has also revealed that, where it is technologically sensible, process controlling computers or microprocessors can be qualified for safety relevant tasks without undue effort. (orig./HP) [de

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

International Nuclear Information System (INIS)

Bertsche, K.; Hoermann, E.

1991-01-01

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

Conversion of Input Data between KENO and MCNP File Formats for Computer Criticality Assessments

International Nuclear Information System (INIS)

Schwarz, Randolph A.; Carter, Leland L.; Schwarz Alysia L.

2006-01-01

KENO is a Monte Carlo criticality code that is maintained by Oak Ridge National Laboratory (ORNL). KENO is included in the SCALE (Standardized Computer Analysis for Licensing Evaluation) package. KENO is often used because it was specifically designed for criticality calculations. Because KENO has convenient geometry input, including the treatment of lattice arrays of materials, it is frequently used for production calculations. Monte Carlo N-Particle (MCNP) is a Monte Carlo transport code maintained by Los Alamos National Laboratory (LANL). MCNP has a powerful 3D geometry package and an extensive cross section database. It is a general-purpose code and may be used for calculations involving shielding or medical facilities, for example, but can also be used for criticality calculations. MCNP is becoming increasingly more popular for performing production criticality calculations. Both codes have their own specific advantages. After a criticality calculation has been performed with one of the codes, it is often desirable (or may be a safety requirement) to repeat the calculation with the other code to compare the important parameters using a different geometry treatment and cross section database. This manual conversion of input files between the two codes is labor intensive. The industry needs the capability of converting geometry models between MCNP and KENO without a large investment in manpower. The proposed conversion package will aid the user in converting between the codes. It is not intended to be used as a ''black box''. The resulting input file will need to be carefully inspected by criticality safety personnel to verify the intent of the calculation is preserved in the conversion. The purpose of this package is to help the criticality specialist in the conversion process by converting the geometry, materials, and pertinent data cards

USSR orders computers to improve nuclear safety

International Nuclear Information System (INIS)

Anon.

1990-01-01

Control Data Corp (CDC) has received an order valued at $32-million from the Soviet Union for six Cyber 962 mainframe computer systems to be used to increase the safety of civilian nuclear powerplants. The firm is now waiting for approval of the contract by the US government and Western Allies. The computers, ordered by the Soviet Research and Development Institute of Power Engineering (RDIPE), will analyze safety factors in the operation of nuclear reactors over a wide range of conditions. The Soviet Union's civilian nuclear program is one of the largest in the world, with over 50 plants in operation. Types of safety analyses the computers perform include: neutron-physics calculations, radiation-protection studies, stress analysis, reliability analysis of equipment and systems, ecological-impact calculations, transient analysis, and support activities for emergency response. They also include a simulator with realistic mathematical models of Soviet nuclear powerplants to improve operator training

Long term file migration. Part I: file reference patterns

International Nuclear Information System (INIS)

Smith, A.J.

1978-08-01

In most large computer installations, files are moved between on-line disk and mass storage (tape, integrated mass storage device) either automatically by the system or specifically at the direction of the user. This is the first of two papers which study the selection of algorithms for the automatic migration of files between mass storage and disk. The use of the text editor data sets at the Stanford Linear Accelerator Center (SLAC) computer installation is examined through the analysis of thirteen months of file reference data. Most files are used very few times. Of those that are used sufficiently frequently that their reference patterns may be examined, about a third show declining rates of reference during their lifetime; of the remainder, very few (about 5%) show correlated interreference intervals, and interreference intervals (in days) appear to be more skewed than would occur with the Bernoulli process. Thus, about two-thirds of all sufficiently active files appear to be referenced as a renewal process with a skewed interreference distribution. A large number of other file reference statistics (file lifetimes, interference distributions, moments, means, number of uses/file, file sizes, file rates of reference, etc.) are computed and presented. The results are applied in the following paper to the development and comparative evaluation of file migration algorithms. 17 figures, 13 tables

Improving operational safety management through probabilistic safety assessment on personal computers

International Nuclear Information System (INIS)

1988-10-01

The Technical Committee Meeting considered the current effort in the implementation and use of PSA information for day-to-day operational safety management on Personal Computers. Due to the very recent development of the necessary hardware and software for Personal Computers, the application of PSA information for day-to-day operational safety management on PCs is essentially still in a pioneering stage. There is at present only one such system for end users existing, the PRISIM (Plant Risk Status Information Management) program for which a limited practical application experience is available. Others are still in the development stage. The main aim of the Technical Committee Meeting was to discuss the present status of PSA based systems for operational safety management support on small computers, to consider practical aspects when implementing these systems into a nuclear installation and to address problems related to the further work in the area. A separate abstract was prepared for the summary of the Technical Committee Meeting and for the 8 papers presented by the participants. Refs, figs and tabs

Overview of Risk Mitigation for Safety-Critical Computer-Based Systems

Science.gov (United States)

Torres-Pomales, Wilfredo

2015-01-01

This report presents a high-level overview of a general strategy to mitigate the risks from threats to safety-critical computer-based systems. In this context, a safety threat is a process or phenomenon that can cause operational safety hazards in the form of computational system failures. This report is intended to provide insight into the safety-risk mitigation problem and the characteristics of potential solutions. The limitations of the general risk mitigation strategy are discussed and some options to overcome these limitations are provided. This work is part of an ongoing effort to enable well-founded assurance of safety-related properties of complex safety-critical computer-based aircraft systems by developing an effective capability to model and reason about the safety implications of system requirements and design.

Safety Metrics for Human-Computer Controlled Systems

Science.gov (United States)

Leveson, Nancy G; Hatanaka, Iwao

2000-01-01

The rapid growth of computer technology and innovation has played a significant role in the rise of computer automation of human tasks in modem production systems across all industries. Although the rationale for automation has been to eliminate "human error" or to relieve humans from manual repetitive tasks, various computer-related hazards and accidents have emerged as a direct result of increased system complexity attributed to computer automation. The risk assessment techniques utilized for electromechanical systems are not suitable for today's software-intensive systems or complex human-computer controlled systems.This thesis will propose a new systemic model-based framework for analyzing risk in safety-critical systems where both computers and humans are controlling safety-critical functions. A new systems accident model will be developed based upon modem systems theory and human cognitive processes to better characterize system accidents, the role of human operators, and the influence of software in its direct control of significant system functions Better risk assessments will then be achievable through the application of this new framework to complex human-computer controlled systems.

Computer aided safety analysis

International Nuclear Information System (INIS)

1988-05-01

The document reproduces 20 selected papers from the 38 papers presented at the Technical Committee/Workshop on Computer Aided Safety Analysis organized by the IAEA in co-operation with the Institute of Atomic Energy in Otwock-Swierk, Poland on 25-29 May 1987. A separate abstract was prepared for each of these 20 technical papers. Refs, figs and tabs

A Computer Program for Assessing Nuclear Safety Culture Impact

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-15

Through several accidents of NPP including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, a lack of safety culture was pointed out as one of the root cause of these accidents. Due to its latent influences on safety performance, safety culture has become an important issue in safety researches. Most of the researches describe how to evaluate the state of the safety culture of the organization. However, they did not include a possibility that the accident occurs due to the lack of safety culture. Because of that, a methodology for evaluating the impact of the safety culture on NPP's safety is required. In this study, the methodology for assessing safety culture impact is suggested and a computer program is developed for its application. SCII model which is the new methodology for assessing safety culture impact quantitatively by using PSA model. The computer program is developed for its application. This program visualizes the SCIs and the SCIIs. It might contribute to comparing the level of the safety culture among NPPs as well as improving the management safety of NPP.

Applications of computer based safety systems in Korea nuclear power plants

International Nuclear Information System (INIS)

Won Young Yun

1998-01-01

With the progress of computer technology, the applications of computer based safety systems in Korea nuclear power plants have increased rapidly in recent decades. The main purpose of this movement is to take advantage of modern computer technology so as to improve the operability and maintainability of the plants. However, in fact there have been a lot of controversies on computer based systems' safety between the regulatory body and nuclear utility in Korea. The Korea Institute of Nuclear Safety (KINS), technical support organization for nuclear plant licensing, is currently confronted with the pressure to set up well defined domestic regulatory requirements from this aspect. This paper presents the current status and the regulatory activities related to the applications of computer based safety systems in Korea. (author)

Making nuclear power plant operational decisions using probabilistic safety assessment information and personal computers. Working material

International Nuclear Information System (INIS)

1991-01-01

PRISIM described in this case study makes a PSA useful to decision makers like plant managers, operational personnel or safety assessors because it provides a rapid access to specific information and the ability to generate updated PSA results that reflect the plant status at a particular time. From the capabilities of PRISIM one can conclude that the ability of a user friendly update of the system model in the PC or changes in the data files at the computer is not realized to data. Also the calculation of averaged probabilities instead of time dependent instantaneous probabilities is a sort of a restriction and will be changed in the future. 5 refs, 34 figs, 3 tabs

29 CFR 1977.15 - Filing of complaint for discrimination.

Science.gov (United States)

2010-07-01

... OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 Procedures § 1977.15 Filing of complaint for discrimination. (a) Who... 1977.15 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION... required. (c) Place of filing. Complaint should be filed with the Area Director (Occupational Safety and...

File and metadata management for BESIII distributed computing

International Nuclear Information System (INIS)

Nicholson, C; Zheng, Y H; Lin, L; Deng, Z Y; Li, W D; Zhang, X M

2012-01-01

The BESIII experiment at the Institute of High Energy Physics (IHEP), Beijing, uses the high-luminosity BEPCII e + e − collider to study physics in the π-charm energy region around 3.7 GeV; BEPCII has produced the worlds largest samples of J/φ and φ’ events to date. An order of magnitude increase in the data sample size over the 2011-2012 data-taking period demanded a move from a very centralized to a distributed computing environment, as well as the development of an efficient file and metadata management system. While BESIII is on a smaller scale than some other HEP experiments, this poses particular challenges for its distributed computing and data management system. These constraints include limited resources and manpower, and low quality of network connections to IHEP. Drawing on the rich experience of the HEP community, a system has been developed which meets these constraints. The design and development of the BESIII distributed data management system, including its integration with other BESIII distributed computing components, such as job management, are presented here.

Role of computer techniques for knowledge propagation about nuclear energetics safety

International Nuclear Information System (INIS)

Osachkin, V.S.

1996-01-01

The development of nuclear power engineering depends on the levels of nuclear, radiological and ecological safety. To ensure the approval of such levels by the community to spread the knowledge on Safety of Nuclear Engineering in understandable forms. New computer technologies may play an important role in the safety education of the public and upgrading of qualification of personnel. The progress in computer nets development makes it possible to use besides e-mail qualification of personnel. The progress in computer in nets development makes it possible to use besides e-mail and BBS the Internet system for remote education. As an example a computer course on Atomic Energy and its safety presented. This course now written in Russian consists of 6 parts, namely: physical basis of utilization of Nuclear energy; technical bases of uses of Nuclear energy; nuclear Reactors and their Systems; safety Principles, Goals, Nuclear Safety Regulation; the Environmental Impact of the us of Nuclear Power, severe accident consequences and scenarios

Transfer of numeric ASCII data files between Apple and IBM personal computers.

Science.gov (United States)

Allan, R W; Bermejo, R; Houben, D

1986-01-01

Listings for programs designed to transfer numeric ASCII data files between Apple and IBM personal computers are provided with accompanying descriptions of how the software operates. Details of the hardware used are also given. The programs may be easily adapted for transferring data between other microcomputers.

Computer codes for level 1 probabilistic safety assessment

International Nuclear Information System (INIS)

1990-06-01

Probabilistic Safety Assessment (PSA) entails several laborious tasks suitable for computer codes assistance. This guide identifies these tasks, presents guidelines for selecting and utilizing computer codes in the conduct of the PSA tasks and for the use of PSA results in safety management and provides information on available codes suggested or applied in performing PSA in nuclear power plants. The guidance is intended for use by nuclear power plant system engineers, safety and operating personnel, and regulators. Large efforts are made today to provide PC-based software systems and PSA processed information in a way to enable their use as a safety management tool by the nuclear power plant overall management. Guidelines on the characteristics of software needed for management to prepare a software that meets their specific needs are also provided. Most of these computer codes are also applicable for PSA of other industrial facilities. The scope of this document is limited to computer codes used for the treatment of internal events. It does not address other codes available mainly for the analysis of external events (e.g. seismic analysis) flood and fire analysis. Codes discussed in the document are those used for probabilistic rather than for phenomenological modelling. It should be also appreciated that these guidelines are not intended to lead the user to selection of one specific code. They provide simply criteria for the selection. Refs and tabs

Heat Transfer treatment in computer codes for safety analysis

International Nuclear Information System (INIS)

Jerele, A.; Gregoric, M.

1984-01-01

Increased number of operating nuclear power plants has stressed importance of nuclear safety evaluation. For this reason, accordingly to regulatory commission request, safety analyses with computer codes are preformed. In this paper part of this thermohydraulic models dealing with wall-to-fluid heat transfer correlations in computer codes TRAC=PF1, RELAP4/MOD5, RELAP5/MOD1 and COBRA-IV is discussed. (author)

Analysis of Critical Characteristics for Safety Graded Personnel Computers in the KNICS Architecture

International Nuclear Information System (INIS)

Lee, Hyun Chul; Lee, Dong Young

2009-01-01

Critical characteristics analysis of a safety related item is to identify characteristics to be verified to replace an original item with the dedicated item. It is sure that the dedicated item meeting critical characteristics would perform its intended safety function instead of the specified item. KNICS project developed two safety systems: IDiPS RPS (Reactor Protection System) and IDiPS ESF-CCS (Engineered Safety Features-Component Control System). Two safety systems of IDiPS are equipped with personnel computers, so-called COMs (Cabinet Operator Modules), in their cabinets. The personnel computers, COMs, are responsible for safety system monitoring, testing, and maintaining. Even though two safety systems are safety critical system, the personnel computers of two systems, i.e. COMs, are not graded as safety-graded items. Regulation requirements are expected to be strengthened, and the functions of the personnel computer may be enhanced to include safety-related functions and safety functions, it would be necessary that the grade of the personnel computers is adjusted to a higher level, the safety grade. To try to upgrade a non safety system, i.e. COMs, to a safety system, its safety functions and requirements, i.e. critical characteristics, must be identified and verified. This paper describes the process of the identification of critical characteristics and the results of analysis

Computer graphics in reactor safety analysis

International Nuclear Information System (INIS)

Fiala, C.; Kulak, R.F.

1989-01-01

This paper describes a family of three computer graphics codes designed to assist the analyst in three areas: the modelling of complex three-dimensional finite element models of reactor structures; the interpretation of computational results; and the reporting of the results of numerical simulations. The purpose and key features of each code are presented. The graphics output used in actual safety analysis are used to illustrate the capabilities of each code. 5 refs., 10 figs

Role of computers in CANDU safety systems

International Nuclear Information System (INIS)

Hepburn, G.A.; Gilbert, R.S.; Ichiyen, N.M.

1985-01-01

Small digital computers are playing an expanding role in the safety systems of CANDU nuclear generating stations, both as active components in the trip logic, and as monitoring and testing systems. The paper describes three recent applications: (i) A programmable controller was retro-fitted to Bruce ''A'' Nuclear Generating Station to handle trip setpoint modification as a function of booster rod insertion. (ii) A centralized monitoring computer to monitor both shutdown systems and the Emergency Coolant Injection system, is currently being retro-fitted to Bruce ''A''. (iii) The implementation of process trips on the CANDU 600 design using microcomputers. While not truly a retrofit, this feature was added very late in the design cycle to increase the margin against spurious trips, and has now seen about 4 unit-years of service at three separate sites. Committed future applications of computers in special safety systems are also described. (author)

A Nuclear Safety System based on Industrial Computer

International Nuclear Information System (INIS)

Kim, Ji Hyeon; Oh, Do Young; Lee, Nam Hoon; Kim, Chang Ho; Kim, Jae Hack

2011-01-01

The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

A Nuclear Safety System based on Industrial Computer

Energy Technology Data Exchange (ETDEWEB)

Kim, Ji Hyeon; Oh, Do Young; Lee, Nam Hoon; Kim, Chang Ho; Kim, Jae Hack [Korea Electric Power Corporation Engineering and Construction, Daejeon (Korea, Republic of)

2011-05-15

The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

Risk assessment of computer-controlled safety systems for fusion reactors

International Nuclear Information System (INIS)

Fryer, M.O.; Bruske, S.Z.

1983-01-01

The complexity of fusion reactor systems and the need to display, analyze, and react promptly to large amounts of information during reactor operation will require a number of safety systems in the fusion facilities to be computer controlled. Computer software, therefore, must be included in the reactor safety analyses. Unfortunately, the science of integrating computer software into safety analyses is in its infancy. Combined plant hardware and computer software systems are often treated by making simple assumptions about software performance. This method is not acceptable for assessing risks in the complex fusion systems, and a new technique for risk assessment of combined plant hardware and computer software systems has been developed. This technique is an extension of the traditional fault tree analysis and uses structured flow charts of the software in a manner analogous to wiring or piping diagrams of hardware. The software logic determines the form of much of the fault trees

Reactor safety: the Nova computer system

International Nuclear Information System (INIS)

Eisgruber, H.; Stadelmann, W.

1991-01-01

After instances of maloperation, the causes of defects, the effectiveness of the measures taken to control the situation, and possibilities to avoid future recurrences need to be investigated above all before the plant is restarted. The most important aspect in all these efforts is to check the sequence in time, and the completeness, of the control measures initiated automatically. For this verification, a computer system is used instead of time-consuming manual analytical techniques, which produces the necessary information almost in real time. The results are available within minutes after completion of the measures initiated automatically. As all short-term safety functions are initiated by automatic systems, their consistent and comprehensive verification results in a clearly higher level of safety. The report covers the development of the computer system, and its implementation, in the Gundremmingen nuclear power station. Similar plans are being pursued in Biblis and Muelheim-Kaerlich. (orig.) [de

Trust in social computing. The case of peer-to-peer file sharing networks

Directory of Open Access Journals (Sweden)

Heng Xu

2011-09-01

Full Text Available Social computing and online communities are changing the fundamental way people share information and communicate with each other. Social computing focuses on how users may have more autonomy to express their ideas and participate in social exchanges in various ways, one of which may be peer-to-peer (P2P file sharing. Given the greater risk of opportunistic behavior by malicious or criminal communities in P2P networks, it is crucial to understand the factors that affect individual’s use of P2P file sharing software. In this paper, we develop and empirically test a research model that includes trust beliefs and perceived risks as two major antecedent beliefs to the usage intention. Six trust antecedents are assessed including knowledge-based trust, cognitive trust, and both organizational and peer-network factors of institutional trust. Our preliminary results show general support for the model and offer some important implications for software vendors in P2P sharing industry and regulatory bodies.

Interface design of VSOP'94 computer code for safety analysis

International Nuclear Information System (INIS)

Natsir, Khairina; Andiwijayakusuma, D.; Wahanani, Nursinta Adi; Yazid, Putranto Ilham

2014-01-01

Today, most software applications, also in the nuclear field, come with a graphical user interface. VSOP'94 (Very Superior Old Program), was designed to simplify the process of performing reactor simulation. VSOP is a integrated code system to simulate the life history of a nuclear reactor that is devoted in education and research. One advantage of VSOP program is its ability to calculate the neutron spectrum estimation, fuel cycle, 2-D diffusion, resonance integral, estimation of reactors fuel costs, and integrated thermal hydraulics. VSOP also can be used to comparative studies and simulation of reactor safety. However, existing VSOP is a conventional program, which was developed using Fortran 65 and have several problems in using it, for example, it is only operated on Dec Alpha mainframe platforms and provide text-based output, difficult to use, especially in data preparation and interpretation of results. We develop a GUI-VSOP, which is an interface program to facilitate the preparation of data, run the VSOP code and read the results in a more user friendly way and useable on the Personal 'Computer (PC). Modifications include the development of interfaces on preprocessing, processing and postprocessing. GUI-based interface for preprocessing aims to provide a convenience way in preparing data. Processing interface is intended to provide convenience in configuring input files and libraries and do compiling VSOP code. Postprocessing interface designed to visualized the VSOP output in table and graphic forms. GUI-VSOP expected to be useful to simplify and speed up the process and analysis of safety aspects

Interface design of VSOP'94 computer code for safety analysis

Science.gov (United States)

Natsir, Khairina; Yazid, Putranto Ilham; Andiwijayakusuma, D.; Wahanani, Nursinta Adi

2014-09-01

Today, most software applications, also in the nuclear field, come with a graphical user interface. VSOP'94 (Very Superior Old Program), was designed to simplify the process of performing reactor simulation. VSOP is a integrated code system to simulate the life history of a nuclear reactor that is devoted in education and research. One advantage of VSOP program is its ability to calculate the neutron spectrum estimation, fuel cycle, 2-D diffusion, resonance integral, estimation of reactors fuel costs, and integrated thermal hydraulics. VSOP also can be used to comparative studies and simulation of reactor safety. However, existing VSOP is a conventional program, which was developed using Fortran 65 and have several problems in using it, for example, it is only operated on Dec Alpha mainframe platforms and provide text-based output, difficult to use, especially in data preparation and interpretation of results. We develop a GUI-VSOP, which is an interface program to facilitate the preparation of data, run the VSOP code and read the results in a more user friendly way and useable on the Personal 'Computer (PC). Modifications include the development of interfaces on preprocessing, processing and postprocessing. GUI-based interface for preprocessing aims to provide a convenience way in preparing data. Processing interface is intended to provide convenience in configuring input files and libraries and do compiling VSOP code. Postprocessing interface designed to visualized the VSOP output in table and graphic forms. GUI-VSOP expected to be useful to simplify and speed up the process and analysis of safety aspects.

Computer-based and web-based radiation safety training

Energy Technology Data Exchange (ETDEWEB)

Owen, C., LLNL

1998-03-01

The traditional approach to delivering radiation safety training has been to provide a stand-up lecture of the topic, with the possible aid of video, and to repeat the same material periodically. New approaches to meeting training requirements are needed to address the advent of flexible work hours and telecommuting, and to better accommodate individuals learning at their own pace. Computer- based and web-based radiation safety training can provide this alternative. Computer-based and web- based training is an interactive form of learning that the student controls, resulting in enhanced and focused learning at a time most often chosen by the student.

An analysis of file system and installation of the file management system for NOS operating system

International Nuclear Information System (INIS)

Lee, Young Jai; Park, Sun Hee; Hwang, In Ah; Kim, Hee Kyung

1992-06-01

In this technical report, we analyze NOS file structure for Cyber 170-875 and Cyber 960-31 computer system. We also describe functions, procedure and how-to-operate and how-to-use of VDS. VDS is used to manage large files effectively for Cyber computer system. The purpose of the VDS installation is to increase the virtual disk storage by utilizing magnetic tape, to assist the users of the computer system in managing their files, and to enhance the performance of KAERI Cyber computer system. (Author)

Safety tests file

International Nuclear Information System (INIS)

2011-01-01

The design and operation of nuclear power plants is governed by strict and clearly defined regulations designed to ensure their safety in all circumstances. Since the first nuclear reactors were commissioned, the basic safety principles and the corresponding practical requirements have constantly evolved and been enhanced, benefiting from operating experience feedback from reactors around the world (about 500 production reactors currently in service). Reactor safety has from the outset been built around the 'defense in depth' concept, which aims to prevent melting of the core and radioactive releases into the environment. It can be summarized as follows: over and above all the measures taken to prevent accidents, the principle that accidents do occur has to be accepted. We then assess their consequences and take steps to contain them at the level of severity at which they occur. (authors)

Bibliography for computer security, integrity, and safety

Science.gov (United States)

Bown, Rodney L.

1991-01-01

A bibliography of computer security, integrity, and safety issues is given. The bibliography is divided into the following sections: recent national publications; books; journal, magazine articles, and miscellaneous reports; conferences, proceedings, and tutorials; and government documents and contractor reports.

Dimensional quality control of Ti-Ni dental file by optical coordinate metrology and computed tomography

DEFF Research Database (Denmark)

Yagüe-Fabra, J.A.; Tosello, Guido; Ontiveros, S.

2014-01-01

Endodontic dental files usually present complex 3D geometries, which make the complete measurement of the component very challenging with conventional micro metrology tools. Computed Tomography (CT) can represent a suitable alternative solution to micro metrology tools based on optical and tactile...... techniques. However, the establishment of CT systems traceability when measuring 3D complex geometries is still an open issue. In this work, to verify the quality of the CT dimensional measurements, the dental file has been measured both with a μCT system and an optical CMM (OCMM). The uncertainty...

Safety Computer Vision Rules for Improved Sensor Certification

DEFF Research Database (Denmark)

Mogensen, Johann Thor Ingibergsson; Kraft, Dirk; Schultz, Ulrik Pagh

2017-01-01

Mobile robots are used across many domains from personal care to agriculture. Working in dynamic open-ended environments puts high constraints on the robot perception system, which is critical for the safety of the system as a whole. To achieve the required safety levels the perception system needs...... to be certified, but no specific standards exist for computer vision systems, and the concept of safe vision systems remains largely unexplored. In this paper we present a novel domain-specific language that allows the programmer to express image quality detection rules for enforcing safety constraints...

PCF File Format.

Energy Technology Data Exchange (ETDEWEB)

Thoreson, Gregory G [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-08-01

PCF files are binary files designed to contain gamma spectra and neutron count rates from radiation sensors. It is the native format for the GAmma Detector Response and Analysis Software (GADRAS) package [1]. It can contain multiple spectra and information about each spectrum such as energy calibration. This document outlines the format of the file that would allow one to write a computer program to parse and write such files.

Interface design of VSOP'94 computer code for safety analysis

Energy Technology Data Exchange (ETDEWEB)

Natsir, Khairina, E-mail: yenny@batan.go.id; Andiwijayakusuma, D.; Wahanani, Nursinta Adi [Center for Development of Nuclear Informatics - National Nuclear Energy Agency, PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia); Yazid, Putranto Ilham [Center for Nuclear Technology, Material and Radiometry- National Nuclear Energy Agency, Jl. Tamansari No.71, Bandung 40132 (Indonesia)

2014-09-30

Today, most software applications, also in the nuclear field, come with a graphical user interface. VSOP'94 (Very Superior Old Program), was designed to simplify the process of performing reactor simulation. VSOP is a integrated code system to simulate the life history of a nuclear reactor that is devoted in education and research. One advantage of VSOP program is its ability to calculate the neutron spectrum estimation, fuel cycle, 2-D diffusion, resonance integral, estimation of reactors fuel costs, and integrated thermal hydraulics. VSOP also can be used to comparative studies and simulation of reactor safety. However, existing VSOP is a conventional program, which was developed using Fortran 65 and have several problems in using it, for example, it is only operated on Dec Alpha mainframe platforms and provide text-based output, difficult to use, especially in data preparation and interpretation of results. We develop a GUI-VSOP, which is an interface program to facilitate the preparation of data, run the VSOP code and read the results in a more user friendly way and useable on the Personal 'Computer (PC). Modifications include the development of interfaces on preprocessing, processing and postprocessing. GUI-based interface for preprocessing aims to provide a convenience way in preparing data. Processing interface is intended to provide convenience in configuring input files and libraries and do compiling VSOP code. Postprocessing interface designed to visualized the VSOP output in table and graphic forms. GUI-VSOP expected to be useful to simplify and speed up the process and analysis of safety aspects.

Computer security at ukrainian nuclear facilities: interface between nuclear safety and security

International Nuclear Information System (INIS)

Chumak, D.; Klevtsov, O.

2015-01-01

Active introduction of information technology, computer instrumentation and control systems (I and C systems) in the nuclear field leads to a greater efficiency and management of technological processes at nuclear facilities. However, this trend brings a number of challenges related to cyber-attacks on the above elements, which violates computer security as well as nuclear safety and security of a nuclear facility. This paper considers regulatory support to computer security at the nuclear facilities in Ukraine. The issue of computer and information security considered in the context of physical protection, because it is an integral component. The paper focuses on the computer security of I and C systems important to nuclear safety. These systems are potentially vulnerable to cyber threats and, in case of cyber-attacks, the potential negative impact on the normal operational processes can lead to a breach of the nuclear facility security. While ensuring nuclear security of I and C systems, it interacts with nuclear safety, therefore, the paper considers an example of an integrated approach to the requirements of nuclear safety and security

Safety applications of computer based systems for the process industry

International Nuclear Information System (INIS)

Bologna, Sandro; Picciolo, Giovanni; Taylor, Robert

1997-11-01

Computer based systems, generally referred to as Programmable Electronic Systems (PESs) are being increasingly used in the process industry, also to perform safety functions. The process industry as they intend in this document includes, but is not limited to, chemicals, oil and gas production, oil refining and power generation. Starting in the early 1970's the wide application possibilities and the related development problems of such systems were recognized. Since then, many guidelines and standards have been developed to direct and regulate the application of computers to perform safety functions (EWICS-TC7, IEC, ISA). Lessons learnt in the last twenty years can be summarised as follows: safety is a cultural issue; safety is a management issue; safety is an engineering issue. In particular, safety systems can only be properly addressed in the overall system context. No single method can be considered sufficient to achieve the safety features required in many safety applications. Good safety engineering approach has to address not only hardware and software problems in isolation but also their interfaces and man-machine interface problems. Finally, the economic and industrial aspects of the safety applications and development of PESs in process plants are evidenced throughout all the Report. Scope of the Report is to contribute to the development of an adequate awareness of these problems and to illustrate technical solutions applied or being developed

File Type Identification of File Fragments using Longest Common Subsequence (LCS)

Science.gov (United States)

Rahmat, R. F.; Nicholas, F.; Purnamawati, S.; Sitompul, O. S.

2017-01-01

Computer forensic analyst is a person in charge of investigation and evidence tracking. In certain cases, the file needed to be presented as digital evidence was deleted. It is difficult to reconstruct the file, because it often lost its header and cannot be identified while being restored. Therefore, a method is required for identifying the file type of file fragments. In this research, we propose Longest Common Subsequences that consists of three steps, namely training, testing and validation, to identify the file type from file fragments. From all testing results we can conlude that our proposed method works well and achieves 92.91% of accuracy to identify the file type of file fragment for three data types.

Comparison of canal transportation and centering ability of twisted files, Pathfile-ProTaper system, and stainless steel hand K-files by using computed tomography.

Science.gov (United States)

Gergi, Richard; Rjeily, Joe Abou; Sader, Joseph; Naaman, Alfred

2010-05-01

The purpose of this study was to compare canal transportation and centering ability of 2 rotary nickel-titanium (NiTi) systems (Twisted Files [TF] and Pathfile-ProTaper [PP]) with conventional stainless steel K-files. Ninety root canals with severe curvature and short radius were selected. Canals were divided randomly into 3 groups of 30 each. After preparation with TF, PP, and stainless steel files, the amount of transportation that occurred was assessed by using computed tomography. Three sections from apical, mid-root, and coronal levels of the canal were recorded. Amount of transportation and centering ability were assessed. The 3 groups were statistically compared with analysis of variance and Tukey honestly significant difference test. Less transportation and better centering ability occurred with TF rotary instruments (P < .0001). K-files showed the highest transportation followed by PP system. PP system showed significant transportation when compared with TF (P < .0001). The TF system was found to be the best for all variables measured in this study. Copyright (c) 2010 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

Using resources for scientific-driven pharmacovigilance: from many product safety documents to one product safety master file.

Science.gov (United States)

Furlan, Giovanni

2012-08-01

required by other documents. The author has identified signal detection (intended not only as adverse event disproportionate reporting, but including non-clinical, laboratory, clinical analysis data and literature screening) and characterization as the basis for the preparation of all drug safety documents, which can be viewed as different ways of presenting the results of this activity. Therefore, the author proposes to merge all the aggregate reports required by current regulations into a single document - the Drug Safety Master File. This report should contain all the available information, from any source, regarding the potential and identified risks of a drug. It should be a living document updated and submitted to regulatory authorities on an ongoing basis.

Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)

International Nuclear Information System (INIS)

1995-09-01

The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: sm-bullet Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) sm-bullet Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as open-quotes lowclose quotes hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with open-quotes moderateclose quotes or open-quotes highclose quotes hazard classifications

Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: {sm_bullet} Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) {sm_bullet} Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as {open_quotes}low{close_quotes} hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with {open_quotes}moderate{close_quotes} or {open_quotes}high{close_quotes} hazard classifications.

Computer Forensics Method in Analysis of Files Timestamps in Microsoft Windows Operating System and NTFS File System

Directory of Open Access Journals (Sweden)

Vesta Sergeevna Matveeva

2013-02-01

Full Text Available All existing file browsers displays 3 timestamps for every file in file system NTFS. Nowadays there are a lot of utilities that can manipulate temporal attributes to conceal the traces of file using. However every file in NTFS has 8 timestamps that are stored in file record and used in detecting the fact of attributes substitution. The authors suggest a method of revealing original timestamps after replacement and automated variant of it in case of a set of files.

Building Parts Inventory Files Using the AppleWorks Data Base Subprogram and Apple IIe or GS Computers.

Science.gov (United States)

Schlenker, Richard M.

This manual is a "how to" training device for building database files using the AppleWorks program with an Apple IIe or Apple IIGS Computer with Duodisk or two disk drives and an 80-column card. The manual provides step-by-step directions, and includes 25 figures depicting the computer screen at the various stages of the database file…

Compendium of computer codes for the safety analysis of LMFBR's

International Nuclear Information System (INIS)

1975-06-01

A high level of mathematical sophistication is required in the safety analysis of LMFBR's to adequately meet the demands for realism and confidence in all areas of accident consequence evaluation. The numerical solution procedures associated with these analyses are generally so complex and time consuming as to necessitate their programming into computer codes. These computer codes have become extremely powerful tools for safety analysis, combining unique advantages in accuracy, speed and cost. The number, diversity and complexity of LMFBR safety codes in the U. S. has grown rapidly in recent years. It is estimated that over 100 such codes exist in various stages of development throughout the country. It is inevitable that such a large assortment of codes will require rigorous cataloguing and abstracting to aid individuals in identifying what is available. It is the purpose of this compendium to provide such a service through the compilation of code summaries which describe and clarify the status of domestic LMFBR safety codes. (U.S.)

Personal computer security: part 1. Firewalls, antivirus software, and Internet security suites.

Science.gov (United States)

Caruso, Ronald D

2003-01-01

Personal computer (PC) security in the era of the Health Insurance Portability and Accountability Act of 1996 (HIPAA) involves two interrelated elements: safeguarding the basic computer system itself and protecting the information it contains and transmits, including personal files. HIPAA regulations have toughened the requirements for securing patient information, requiring every radiologist with such data to take further precautions. Security starts with physically securing the computer. Account passwords and a password-protected screen saver should also be set up. A modern antivirus program can easily be installed and configured. File scanning and updating of virus definitions are simple processes that can largely be automated and should be performed at least weekly. A software firewall is also essential for protection from outside intrusion, and an inexpensive hardware firewall can provide yet another layer of protection. An Internet security suite yields additional safety. Regular updating of the security features of installed programs is important. Obtaining a moderate degree of PC safety and security is somewhat inconvenient but is necessary and well worth the effort. Copyright RSNA, 2003

The Intelligent Safety System: could it introduce complex computing into CANDU shutdown systems

International Nuclear Information System (INIS)

Hall, J.A.; Hinds, H.W.; Pensom, C.F.; Barker, C.J.; Jobse, A.H.

1984-07-01

The Intelligent Safety System is a computerized shutdown system being developed at the Chalk River Nuclear Laboratories (CRNL) for future CANDU nuclear reactors. It differs from current CANDU shutdown systems in both the algorithm used and the size and complexity of computers required to implement the concept. This paper provides an overview of the project, with emphasis on the computing aspects. Early in the project several needs leading to an introduction of computing complexity were identified, and a computing system that met these needs was conceived. The current work at CRNL centers on building a laboratory demonstration of the Intelligent Safety System, and evaluating the reliability and testability of the concept. Some fundamental problems must still be addressed for the Intelligent Safety System to be acceptable to a CANDU owner and to the regulatory authorities. These are also discussed along with a description of how the Intelligent Safety System might solve these problems

European Workshop Industrical Computer Science Systems approach to design for safety

Science.gov (United States)

Zalewski, Janusz

1992-01-01

This paper presents guidelines on designing systems for safety, developed by the Technical Committee 7 on Reliability and Safety of the European Workshop on Industrial Computer Systems. The focus is on complementing the traditional development process by adding the following four steps: (1) overall safety analysis; (2) analysis of the functional specifications; (3) designing for safety; (4) validation of design. Quantitative assessment of safety is possible by means of a modular questionnaire covering various aspects of the major stages of system development.

Use of digital computing devices in systems important to safety

International Nuclear Information System (INIS)

1986-01-01

The incorporation of digital computing devices in systems important to safety now is progressing fast in several countries, including Canada, France, Federal Republic of Germany, Japan, USA. There are now reactors with microprocessors in some trip systems. The major functions of those systems are: reactor trip initiation, display, monitoring, testing, re-calibration of detectors. The benefits of moving to a fully computerized shut-down system should be improved reliability, greater flexibility, better man-machine interface, improved testing, higher reactor output and lower overall cost. With the introduction of computer devices in systems important to safety, plant availability and safety are improved because disturbances are treated before they lead to safety action, in this way helping the operator to avoid errors. The Meeting presentations were divided into sessions devoted to the following topics: Needs for the use of digital devices (DCD) in safety important systems (SIS) (5 papers); Problems raised by the integration SIS in the NPP control (7 papers); Description and presentation of DCD of SIS (6 papers); Results of experiences in engineering, manufacture, qualification operation of DCD hardware and software (5 papers). A separate abstract was prepared for each of these papers

File management for experiment control parameters within a distributed function computer network

International Nuclear Information System (INIS)

Stubblefield, F.W.

1976-10-01

An attempt to design and implement a computer system for control of and data collection from a set of laboratory experiments reveals that many of the experiments in the set require an extensive collection of parameters for their control. The operation of the experiments can be greatly simplified if a means can be found for storing these parameters between experiments and automatically accessing them as they are required. A subsystem for managing files of such experiment control parameters is discussed. 3 figures

Maintaining scale as a realiable computational system for criticality safety analysis

International Nuclear Information System (INIS)

Bowmann, S.M.; Parks, C.V.; Martin, S.K.

1995-01-01

Accurate and reliable computational methods are essential for nuclear criticality safety analyses. The SCALE (Standardized Computer Analyses for Licensing Evaluation) computer code system was originally developed at Oak Ridge National Laboratory (ORNL) to enable users to easily set up and perform criticality safety analyses, as well as shielding, depletion, and heat transfer analyses. Over the fifteen-year life of SCALE, the mainstay of the system has been the criticality safety analysis sequences that have featured the KENO-IV and KENO-V.A Monte Carlo codes and the XSDRNPM one-dimensional discrete-ordinates code. The criticality safety analysis sequences provide automated material and problem-dependent resonance processing for each criticality calculation. This report details configuration management which is essential because SCALE consists of more than 25 computer codes (referred to as modules) that share libraries of commonly used subroutines. Changes to a single subroutine in some cases affect almost every module in SCALE exclamation point Controlled access to program source and executables and accurate documentation of modifications are essential to maintaining SCALE as a reliable code system. The modules and subroutine libraries in SCALE are programmed by a staff of approximately ten Code Managers. The SCALE Software Coordinator maintains the SCALE system and is the only person who modifies the production source, executables, and data libraries. All modifications must be authorized by the SCALE Project Leader prior to implementation

The role of CFD computer analyses in hydrogen safety management

International Nuclear Information System (INIS)

Komen, E.M.J; Visser, D.C; Roelofs, F.; Te Lintelo, J.G.T

2014-01-01

The risks of hydrogen release and combustion during a severe accident in a light water reactor have attracted considerable attention after the Fukushima accident in Japan. Reliable computer analyses are needed for the optimal design of hydrogen mitigation systems, like e.g. passive autocatalytic recombiners (PARs), and for the assessment of the associated residual risk of hydrogen combustion. Traditionally, so-called Lumped Parameter (LP) computer codes are being used for these purposes. In the last decade, significant progress has been made in the development, validation, and application of more detailed, three-dimensional Computational Fluid Dynamics (CFD) simulations for hydrogen safety analyses. The objective of the current paper is to address the following questions: - When are CFD computer analyses needed complementary to the traditional LP code analyses for hydrogen safety management? - What is the validation status of the CFD computer code for hydrogen distribution, mitigation, and combustion analyses? - Can CFD computer analyses nowadays be executed in practical and reliable way for full scale containments? The validation status and reliability of CFD code simulations will be illustrated by validation analyses performed for experiments executed in the PANDA, THAI, and ENACCEF facilities. (authors)

Modification to the Monte N-Particle (MCNP) Visual Editor (MCNPVised) to read in Computer Aided Design (CAD) files

International Nuclear Information System (INIS)

Schwarz, Randy A.; Carter, Leeland L.

2004-01-01

Monte Carlo N-Particle Transport Code (MCNP) (Reference 1) is the code of choice for doing complex neutron/photon/electron transport calculations for the nuclear industry and research institutions. The Visual Editor for Monte Carlo N-Particle (References 2 to 11) is recognized internationally as the best code for visually creating and graphically displaying input files for MCNP. The work performed in this grant enhanced the capabilities of the MCNP Visual Editor to allow it to read in a 2D Computer Aided Design (CAD) file, allowing the user to modify and view the 2D CAD file and then electronically generate a valid MCNP input geometry with a user specified axial extent

Shaping ability of the conventional nickel-titanium and reciprocating nickel-titanium file systems: a comparative study using micro-computed tomography.

Science.gov (United States)

Hwang, Young-Hye; Bae, Kwang-Shik; Baek, Seung-Ho; Kum, Kee-Yeon; Lee, WooCheol; Shon, Won-Jun; Chang, Seok Woo

2014-08-01

This study used micro-computed tomographic imaging to compare the shaping ability of Mtwo (VDW, Munich, Germany), a conventional nickel-titanium file system, and Reciproc (VDW), a reciprocating file system morphologically similar to Mtwo. Root canal shaping was performed on the mesiobuccal and distobuccal canals of extracted maxillary molars. In the RR group (n = 15), Reciproc was used in a reciprocating motion (150° counterclockwise/30° clockwise, 300 rpm); in the MR group, Mtwo was used in a reciprocating motion (150° clockwise/30° counterclockwise, 300 rpm); and in the MC group, Mtwo was used in a continuous rotating motion (300 rpm). Micro-computed tomographic images taken before and after canal shaping were used to analyze canal volume change and the degree of transportation at the cervical, middle, and apical levels. The time required for canal shaping was recorded. Afterward, each file was analyzed using scanning electron microscopy. No statistically significant differences were found among the 3 groups in the time for canal shaping or canal volume change (P > .05). Transportation values of the RR and MR groups were not significantly different at any level. However, the transportation value of the MC group was significantly higher than both the RR and MR groups at the cervical and apical levels (P file deformation was observed for 1 file in group RR (1/15), 3 files in group MR (3/15), and 5 files in group MC (5/15). In terms of shaping ability, Mtwo used in a reciprocating motion was not significantly different from the Reciproc system. Copyright © 2014 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

Fast probabilistic file fingerprinting for big data.

Science.gov (United States)

Tretyakov, Konstantin; Laur, Sven; Smant, Geert; Vilo, Jaak; Prins, Pjotr

2013-01-01

Biological data acquisition is raising new challenges, both in data analysis and handling. Not only is it proving hard to analyze the data at the rate it is generated today, but simply reading and transferring data files can be prohibitively slow due to their size. This primarily concerns logistics within and between data centers, but is also important for workstation users in the analysis phase. Common usage patterns, such as comparing and transferring files, are proving computationally expensive and are tying down shared resources. We present an efficient method for calculating file uniqueness for large scientific data files, that takes less computational effort than existing techniques. This method, called Probabilistic Fast File Fingerprinting (PFFF), exploits the variation present in biological data and computes file fingerprints by sampling randomly from the file instead of reading it in full. Consequently, it has a flat performance characteristic, correlated with data variation rather than file size. We demonstrate that probabilistic fingerprinting can be as reliable as existing hashing techniques, with provably negligible risk of collisions. We measure the performance of the algorithm on a number of data storage and access technologies, identifying its strengths as well as limitations. Probabilistic fingerprinting may significantly reduce the use of computational resources when comparing very large files. Utilisation of probabilistic fingerprinting techniques can increase the speed of common file-related workflows, both in the data center and for workbench analysis. The implementation of the algorithm is available as an open-source tool named pfff, as a command-line tool as well as a C library. The tool can be downloaded from http://biit.cs.ut.ee/pfff.

Independent peer review of nuclear safety computer codes

International Nuclear Information System (INIS)

Boyack, B.E.; Jenks, R.P.

1993-01-01

A structured, independent computer code peer-review process has been developed to assist the US Nuclear Regulatory Commission (NRC) and the US Department of Energy in their nuclear safety missions. This paper describes a structured process of independent code peer review, benefits associated with a code-independent peer review, as well as the authors' recent peer-review experience. The NRC adheres to the principle that safety of plant design, construction, and operation are the responsibility of the licensee. Nevertheless, NRC staff must have the ability to independently assess plant designs and safety analyses submitted by license applicants. According to Ref. 1, open-quotes this requires that a sound understanding be obtained of the important physical phenomena that may occur during transients in operating power plants.close quotes The NRC concluded that computer codes are the principal products to open-quotes understand and predict plant response to deviations from normal operating conditionsclose quotes and has developed several codes for that purpose. However, codes cannot be used blindly; they must be assessed and found adequate for the purposes they are intended. A key part of the qualification process can be accomplished through code peer reviews; this approach has been adopted by the NRC

Safety of High Speed Ground Transportation Systems : Analytical Methodology for Safety Validation of Computer Controlled Subsystems : Volume 2. Development of a Safety Validation Methodology

Science.gov (United States)

1995-01-01

This report describes the development of a methodology designed to assure that a sufficiently high level of safety is achieved and maintained in computer-based systems which perform safety cortical functions in high-speed rail or magnetic levitation ...

A secure file manager for UNIX

Energy Technology Data Exchange (ETDEWEB)

DeVries, R.G.

1990-12-31

The development of a secure file management system for a UNIX-based computer facility with supercomputers and workstations is described. Specifically, UNIX in its usual form does not address: (1) Operation which would satisfy rigorous security requirements. (2) Online space management in an environment where total data demands would be many times the actual online capacity. (3) Making the file management system part of a computer network in which users of any computer in the local network could retrieve data generated on any other computer in the network. The characteristics of UNIX can be exploited to develop a portable, secure file manager which would operate on computer systems ranging from workstations to supercomputers. Implementation considerations making unusual use of UNIX features, rather than requiring extensive internal system changes, are described, and implementation using the Cray Research Inc. UNICOS operating system is outlined.

Safety implications of using programmable digital computers in nuclear safety and control systems

International Nuclear Information System (INIS)

Adams, D.M.; Rohrdanz, R.R.

1982-01-01

This papers describes the activities being conducted at the Idaho National Engineering Laboratory associated with the use of stored-program computers for protection and control systems. This project has recently been initiated and a preliminary report will be available. The use of computers in plant control and protection (and more generally in system important to safety) represents a major departure from the systems which have been used in the past. The design, development, and audit methods used for these systems are significantly different, thus requiring different skills and different perspectives

Maintenance of reactor safety and control computers at a large government facility

International Nuclear Information System (INIS)

Brady, H.G.

1985-01-01

In 1950 the US Government contracted the Du Pont Company to design, build, and operate the Savannah River Plant (SRP). At the time, it was the largest construction project ever undertaken by man. It is still the largest of the Department of Energy facilities. In the nearly 35 years that have elapsed, Du Pont has met its commitments to the US Government and set world safety records in the construction and operation of nuclear facilities. Contributing factors in achieving production goals and setting the safety records are a staff of highly qualified personnel, a well maintained plant, and sound maintenance programs. There have been many ''first ever'' achievements at SRP. These ''firsts'' include: (1) computer control of a nuclear rector, and (2) use of computer systems as safety circuits. This presentation discusses the maintenance program provided for these computer systems and all digital systems at SRP. An in-house computer maintenance program that was started in 1966 with five persons has grown to a staff of 40 with investments in computer hardware increasing from $4 million in 1970 to more than $60 million in this decade. 4 figs

Fast reactor safety and computational thermo-fluid dynamics approaches

International Nuclear Information System (INIS)

Ninokata, Hisashi; Shimizu, Takeshi

1993-01-01

This article provides a brief description of the safety principle on which liquid metal cooled fast breeder reactors (LMFBRs) is based and the roles of computations in the safety practices. A number of thermohydraulics models have been developed to date that successfully describe several of the important types of fluids and materials motion encountered in the analysis of postulated accidents in LMFBRs. Most of these models use a mixture of implicit and explicit numerical solution techniques in solving a set of conservation equations formulated in Eulerian coordinates, with special techniques included to specific situations. Typical computational thermo-fluid dynamics approaches are discussed in particular areas of analyses of the physical phenomena relevant to the fuel subassembly thermohydraulics design and that involve describing the motion of molten materials in the core over a large scale. (orig.)

A site of communication among enterprises for supporting occupational health and safety management system.

Science.gov (United States)

Velonakis, E; Mantas, J; Mavrikakis, I

2006-01-01

The occupational health and safety management constitutes a field of increasing interest. Institutions in cooperation with enterprises make synchronized efforts to initiate quality management systems to this field. Computer networks can offer such services via TCP/IP which is a reliable protocol for workflow management between enterprises and institutions. A design of such network is based on several factors in order to achieve defined criteria and connectivity with other networks. The network will be consisted of certain nodes responsible to inform executive persons on Occupational Health and Safety. A web database has been planned for inserting and searching documents, for answering and processing questionnaires. The submission of files to a server and the answers to questionnaires through the web help the experts to make corrections and improvements on their activities. Based on the requirements of enterprises we have constructed a web file server. We submit files in purpose users could retrieve the files which need. The access is limited to authorized users and digital watermarks authenticate and protect digital objects. The Health and Safety Management System follows ISO 18001. The implementation of it, through the web site is an aim. The all application is developed and implemented on a pilot basis for the health services sector. It is all ready installed within a hospital, supporting health and safety management among different departments of the hospital and allowing communication through WEB with other hospitals.

Parallel file system with metadata distributed across partitioned key-value store c

Science.gov (United States)

Bent, John M.; Faibish, Sorin; Grider, Gary; Torres, Aaron

2017-09-19

Improved techniques are provided for storing metadata associated with a plurality of sub-files associated with a single shared file in a parallel file system. The shared file is generated by a plurality of applications executing on a plurality of compute nodes. A compute node implements a Parallel Log Structured File System (PLFS) library to store at least one portion of the shared file generated by an application executing on the compute node and metadata for the at least one portion of the shared file on one or more object storage servers. The compute node is also configured to implement a partitioned data store for storing a partition of the metadata for the shared file, wherein the partitioned data store communicates with partitioned data stores on other compute nodes using a message passing interface. The partitioned data store can be implemented, for example, using Multidimensional Data Hashing Indexing Middleware (MDHIM).

Reactor safety research - visible demonstrations and credible computations

Energy Technology Data Exchange (ETDEWEB)

Loewenstein, W B; Divakaruni, S M

1985-11-01

EPRI has been conducting nuclear safety research for a number of years with the primary goal of assuring the safety and reliability of the nuclear plants. The visibility is emphasized by sponsoring or participating in large scale test demonstrations to credibly support the complex computations that are the basis for quantification of safety margins. Recognizing the success of the airline industry in receiving favorable public perception, the authors compare the design and operation practices of the airline industry with those of the nuclear industry practices to identify the elements contributing to public concerns and unfavorable perceptions. In this paper, authors emphasize the importance of proper communications of research results to the public in a manner that non-specialists understand. Further, EPRI supported research and results in the areas of source term, seismic and structural engineering research, analysis using probabilistic risk assessment (PRA), quantification of safety margins, digital technology development and implementation, and plant transient and performance evaluations are discussed in the paper. (orig./HP).

Reactor safety research - visible demonstrations and credible computations

International Nuclear Information System (INIS)

Loewenstein, W.B.; Divakaruni, S.M.

1985-01-01

EPRI has been conducting nuclear safety research for a number of years with the primary goal of assuring the safety and reliability of the nuclear plants. The visibility is emphasized by sponsoring or participating in large scale test demonstrations to credibly support the complex computations that are the basis for quantification of safety margins. Recognizing the success of the airline industry in receiving favorable public perception, the authors compare the design and operation practices of the airline industry with those of the nuclear industry practices to identify the elements contributing to public concerns and unfavorable perceptions. In this paper, authors emphasize the importance of proper communications of research results to the public in a manner that non-specialists understand. Further, EPRI supported research and results in the areas of source term, seismic and structural engineering research, analysis using probabilistic risk assessment (PRA), quantification of safety margins, digital technology development and implementation, and plant transient and performance evaluations are discussed in the paper. (orig./HP)

School Survey on Crime and Safety (SSOCS) 2000 Public-Use Data Files, User's Manual, and Detailed Data Documentation. [CD-ROM].

Science.gov (United States)

National Center for Education Statistics (ED), Washington, DC.

This CD-ROM contains the raw, public-use data from the 2000 School Survey on Crime and Safety (SSOCS) along with a User's Manual and Detailed Data Documentation. The data are provided in SAS, SPSS, STATA, and ASCII formats. The User's Manual and the Detailed Data Documentation are provided as .pdf files. (Author)

Building a parallel file system simulator

International Nuclear Information System (INIS)

Molina-Estolano, E; Maltzahn, C; Brandt, S A; Bent, J

2009-01-01

Parallel file systems are gaining in popularity in high-end computing centers as well as commercial data centers. High-end computing systems are expected to scale exponentially and to pose new challenges to their storage scalability in terms of cost and power. To address these challenges scientists and file system designers will need a thorough understanding of the design space of parallel file systems. Yet there exist few systematic studies of parallel file system behavior at petabyte- and exabyte scale. An important reason is the significant cost of getting access to large-scale hardware to test parallel file systems. To contribute to this understanding we are building a parallel file system simulator that can simulate parallel file systems at very large scale. Our goal is to simulate petabyte-scale parallel file systems on a small cluster or even a single machine in reasonable time and fidelity. With this simulator, file system experts will be able to tune existing file systems for specific workloads, scientists and file system deployment engineers will be able to better communicate workload requirements, file system designers and researchers will be able to try out design alternatives and innovations at scale, and instructors will be able to study very large-scale parallel file system behavior in the class room. In this paper we describe our approach and provide preliminary results that are encouraging both in terms of fidelity and simulation scalability.

Reciprocating vs Rotary Instrumentation in Pediatric Endodontics: Cone Beam Computed Tomographic Analysis of Deciduous Root Canals using Two Single-file Systems.

Science.gov (United States)

Prabhakar, Attiguppe R; Yavagal, Chandrashekar; Dixit, Kratika; Naik, Saraswathi V

2016-01-01

Primary root canals are considered to be most challenging due to their complex anatomy. "Wave one" and "one shape" are single-file systems with reciprocating and rotary motion respectively. The aim of this study was to evaluate and compare dentin thickness, centering ability, canal transportation, and instrumentation time of wave one and one shape files in primary root canals using a cone beam computed tomographic (CBCT) analysis. This is an experimental, in vitro study comparing the two groups. A total of 24 extracted human primary teeth with minimum 7 mm root length were included in the study. Cone beam computed tomographic images were taken before and after the instrumentation for each group. Dentin thickness, centering ability, canal transportation, and instrumentation times were evaluated for each group. A significant difference was found in instrumentation time and canal transportation measures between the two groups. Wave one showed less canal transportation as compared with one shape, and the mean instrumentation time of wave one was significantly less than one shape. Reciprocating single-file systems was found to be faster with much less procedural errors and can hence be recommended for shaping the root canals of primary teeth. How to cite this article: Prabhakar AR, Yavagal C, Dixit K, Naik SV. Reciprocating vs Rotary Instrumentation in Pediatric Endodontics: Cone Beam Computed Tomographic Analysis of Deciduous Root Canals using Two Single-File Systems. Int J Clin Pediatr Dent 2016;9(1):45-49.

Modeling of requirement specification for safety critical real time computer system using formal mathematical specifications

International Nuclear Information System (INIS)

Sankar, Bindu; Sasidhar Rao, B.; Ilango Sambasivam, S.; Swaminathan, P.

2002-01-01

Full text: Real time computer systems are increasingly used for safety critical supervision and control of nuclear reactors. Typical application areas are supervision of reactor core against coolant flow blockage, supervision of clad hot spot, supervision of undesirable power excursion, power control and control logic for fuel handling systems. The most frequent cause of fault in safety critical real time computer system is traced to fuzziness in requirement specification. To ensure the specified safety, it is necessary to model the requirement specification of safety critical real time computer systems using formal mathematical methods. Modeling eliminates the fuzziness in the requirement specification and also helps to prepare the verification and validation schemes. Test data can be easily designed from the model of the requirement specification. Z and B are the popular languages used for modeling the requirement specification. A typical safety critical real time computer system for supervising the reactor core of prototype fast breeder reactor (PFBR) against flow blockage is taken as case study. Modeling techniques and the actual model are explained in detail. The advantages of modeling for ensuring the safety are summarized

South Ukraine NPP: Safety improvements through Plant Computer upgrade

International Nuclear Information System (INIS)

Brenman, O.; Chernyshov, M. A.; Denning, R. S.; Kolesov, S. A.; Balakan, H. H.; Bilyk, B. I.; Kuznetsov, V. I.; Trosman, G.

2006-01-01

This paper summarizes some results of the Plant Computer upgrade at the Units 2 and 3 of South Ukraine Nuclear Power Plant (NPP). A Plant Computer, which is also called the Computer Information System (CIS), is one of the key safety-related systems at VVER-1000 nuclear plants. The main function of the CIS is information support for the plant operators during normal and emergency operational modes. Before this upgrade, South Ukraine NPP operated out-of-date and obsolete systems. This upgrade project wax founded by the U.S. DOE in the framework of the International Nuclear Safety Program (INSP). The most efficient way to improve the quality and reliability of information provided to the plant operator is to upgrade the Human-System Interface (HSI), which is the Upper Level (UL) CIS. The upgrade of the CIS data-acquisition system (DAS), which is the Lower Level (LL) CIS, would have less effect on the unit safety. Generally speaking, the lifetime of the LL CIS is much higher than one of the UL CIS. Unlike Plant Computers at the Western-designed plants, the functionality of the WER-1000 CISs includes a control function (Centralized Protection Testing) and a number of the plant equipment monitoring functions, for example, Protection and Interlock Monitoring and Turbo-Generator Temperature Monitoring. The new system is consistent with a historical migration of the format by which information is presented to the operator away from the traditional graphic displays, for example, Piping and Instrument Diagrams (P and ID's), toward Integral Data displays. The cognitive approach to information presentation is currently limited by some licensing issues, but is adapted to a greater degree with each new system. The paper provides some lessons learned on the management of the international team. (authors)

Computational methods for nuclear criticality safety analysis

International Nuclear Information System (INIS)

Maragni, M.G.

1992-01-01

Nuclear criticality safety analyses require the utilization of methods which have been tested and verified against benchmarks results. In this work, criticality calculations based on the KENO-IV and MCNP codes are studied aiming the qualification of these methods at the IPEN-CNEN/SP and COPESP. The utilization of variance reduction techniques is important to reduce the computer execution time, and several of them are analysed. As practical example of the above methods, a criticality safety analysis for the storage tubes for irradiated fuel elements from the IEA-R1 research has been carried out. This analysis showed that the MCNP code is more adequate for problems with complex geometries, and the KENO-IV code shows conservative results when it is not used the generalized geometry option. (author)

Generation of Gaussian 09 Input Files for the Computation of 1H and 13C NMR Chemical Shifts of Structures from a Spartan’14 Conformational Search

OpenAIRE

sprotocols

2014-01-01

Authors: Spencer Reisbick & Patrick Willoughby ### Abstract This protocol describes an approach to preparing a series of Gaussian 09 computational input files for an ensemble of conformers generated in Spartan’14. The resulting input files are necessary for computing optimum geometries, relative conformer energies, and NMR shielding tensors using Gaussian. Using the conformational search feature within Spartan’14, an ensemble of conformational isomers was obtained. To convert the str...

Research of Performance Linux Kernel File Systems

Directory of Open Access Journals (Sweden)

Andrey Vladimirovich Ostroukh

2015-10-01

Full Text Available The article describes the most common Linux Kernel File Systems. The research was carried out on a personal computer, the characteristics of which are written in the article. The study was performed on a typical workstation running GNU/Linux with below characteristics. On a personal computer for measuring the file performance, has been installed the necessary software. Based on the results, conclusions and proposed recommendations for use of file systems. Identified and recommended by the best ways to store data.

Development of computer program for safety of nuclear power plant against tsunami

International Nuclear Information System (INIS)

Jin, S. B.; Choi, K. R.; Lee, S. K.; Cho, Y. S.

2001-01-01

The main objective of this study is the development of a computer program to check the safety of nuclear power plants along the coastline of the Korean Peninsula. The computer program describes the propagation and associated run-up process of tsunamis by solving linear and nonlinear shallow-water equations with finite difference methods. The computer program has been applied to several ideal and simplified problems. Obtained numerical solutions are compared to existing and available solutions and measurements. A very good agreement between numerical solutions and existing measurement is observed. The computer program developed in this study can be to check the safety analysis of nuclear power plants against tsunamis. The program can also be used to study the propagation of tsunamis for a long distance, and associated run-up and run-down process along a shoreline. Furthermore, the computer program can be used to provide the proper design criteria of coastal facilities and structures

Development of a quality assurance safety assessment database for near surface radioactive waste disposal

International Nuclear Information System (INIS)

Park, J. W.; Kim, C. L.; Park, J. B.; Lee, E. Y.; Lee, Y. M.; Kang, C. H.; Zhou, W.; Kozak, M. W.

2003-01-01

A quality assurance safety assessment database, called QUARK (QUality Assurance program for Radioactive waste management in Korea), has been developed to manage both analysis information and parameter database for safety assessment of Low- and Intermediate-Level radioactive Waste (LILW) disposal facility in Korea. QUARK is such a tool that serves QA purposes for managing safety assessment information properly and securely. In QUARK, the information is organized and linked to maximize the integrity of information and traceability. QUARK provides guidance to conduct safety assessment analysis, from scenario generation to result analysis, and provides a window to inspect and trace previous safety assessment analysis and parameter values. QUARK also provides default database for safety assessment staff who construct input data files using SAGE(Safety Assessment Groundwater Evaluation), a safety assessment computer code

Computer automation of a health physics program record

International Nuclear Information System (INIS)

Bird, E.M.; Flook, B.A.; Jarrett, R.D.

1984-01-01

A multi-user computer data base management system (DBMS) has been developed to automate USDA's national radiological safety program. It maintains information on approved users of radioactive material and radiation emanating equipment, as a central file which is accessed whenever information on the user is required. Files of inventory, personnel dosemetry records, laboratory and equipment surveys, leak tests, bioassay reports, and all other information are linked to each approved user by an assigned code that identifies the user by state, agency, and facility. The DBMS is menu-driven with provisions for addition, modification and report generation of information maintained in the system. This DBMS was designed as a single entry system to reduce the redundency of data entry. Prompts guide the user at decision points and data validation routines check for proper data entry. The DBMS generates lists of current inventories, leak test forms, inspection reports, scans for overdue reports from users, and generates follow-up letters. The DBMS system operates on a Wang OIS computer and utilizes its compiled BASIC, List Processing, Word Processing, and indexed (ISAM) file features. This system is a very fast relational database supporting many users simultaneously while providing several methods of data protection. All data files are compatible with List Processing. Information in these files can be examined, sorted, modified, or outputted to word processing documents using software supplied by Wang. This has reduced the need for special one-time programs and provides alternative access to the data

Extracting the Data From the LCM vk4 Formatted Output File

Energy Technology Data Exchange (ETDEWEB)

Wendelberger, James G. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2018-01-29

These are slides about extracting the data from the LCM vk4 formatted output file. The following is covered: vk4 file produced by Keyence VK Software, custom analysis, no off the shelf way to read the file, reading the binary data in a vk4 file, various offsets in decimal lines, finding the height image data, directly in MATLAB, binary output beginning of height image data, color image information, color image binary data, color image decimal and binary data, MATLAB code to read vk4 file (choose a file, read the file, compute offsets, read optical image, laser optical image, read and compute laser intensity image, read height image, timing, display height image, display laser intensity image, display RGB laser optical images, display RGB optical images, display beginning data and save images to workspace, gamma correction subroutine), reading intensity form the vk4 file, linear in the low range, linear in the high range, gamma correction for vk4 files, computing the gamma intensity correction, observations.

A Safety Resource Allocation Mechanism against Connection Fault for Vehicular Cloud Computing

Directory of Open Access Journals (Sweden)

Tianpeng Ye

2016-01-01

Full Text Available The Intelligent Transportation System (ITS becomes an important component of the smart city toward safer roads, better traffic control, and on-demand service by utilizing and processing the information collected from sensors of vehicles and road side infrastructure. In ITS, Vehicular Cloud Computing (VCC is a novel technology balancing the requirement of complex services and the limited capability of on-board computers. However, the behaviors of the vehicles in VCC are dynamic, random, and complex. Thus, one of the key safety issues is the frequent disconnections between the vehicle and the Vehicular Cloud (VC when this vehicle is computing for a service. More important, the connection fault will disturb seriously the normal services of VCC and impact the safety works of the transportation. In this paper, a safety resource allocation mechanism is proposed against connection fault in VCC by using a modified workflow with prediction capability. We firstly propose the probability model for the vehicle movement which satisfies the high dynamics and real-time requirements of VCC. And then we propose a Prediction-based Reliability Maximization Algorithm (PRMA to realize the safety resource allocation for VCC. The evaluation shows that our mechanism can improve the reliability and guarantee the real-time performance of the VCC.

77 FR 50720 - Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Science.gov (United States)

2012-08-22

... Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft... Computer Software used in Safety Systems of Nuclear Power Plants.'' The DG-1207 is proposed Revision 1 of... for Digital Computer Software Used in Safety Systems of Nuclear Power Plants'' is temporarily...

Design and installation of advanced computer safety related instrumentation

International Nuclear Information System (INIS)

Koch, S.; Andolina, K.; Ruether, J.

1993-01-01

The rapidly developing area of computer systems creates new opportunities for commercial utilities operating nuclear reactors to improve plant operation and efficiency. Two of the main obstacles to utilizing the new technology in safety-related applications is the current policy of the licensing agencies and the fear of decision making managers to introduce new technologies. Once these obstacles are overcome, advanced diagnostic systems, CRT-based displays, and advanced communication channels can improve plant operation considerably. The article discusses outstanding issues in the area of designing, qualifying, and licensing of computer-based instrumentation and control systems. The authors describe the experience gained in designing three safety-related systems, that include a Programmable Logic Controller (PLC) based Safeguard Load Sequencer for NSP Prairie Island, a digital Containment Isolation monitoring system for TVA Browns Ferry, and a study that was conducted for EPRI/NSP regarding a PLC-based Reactor Protection system. This article presents the benefits to be gained in replacing existing, outdated equipment with new advanced instrumentation

Cloud/Fog Computing System Architecture and Key Technologies for South-North Water Transfer Project Safety

Directory of Open Access Journals (Sweden)

Yaoling Fan

2018-01-01

Full Text Available In view of the real-time and distributed features of Internet of Things (IoT safety system in water conservancy engineering, this study proposed a new safety system architecture for water conservancy engineering based on cloud/fog computing and put forward a method of data reliability detection for the false alarm caused by false abnormal data from the bottom sensors. Designed for the South-North Water Transfer Project (SNWTP, the architecture integrated project safety, water quality safety, and human safety. Using IoT devices, fog computing layer was constructed between cloud server and safety detection devices in water conservancy projects. Technologies such as real-time sensing, intelligent processing, and information interconnection were developed. Therefore, accurate forecasting, accurate positioning, and efficient management were implemented as required by safety prevention of the SNWTP, and safety protection of water conservancy projects was effectively improved, and intelligential water conservancy engineering was developed.

CADRIGS--computer aided design reliability interactive graphics system

International Nuclear Information System (INIS)

Kwik, R.J.; Polizzi, L.M.; Sticco, S.; Gerrard, P.B.; Yeater, M.L.; Hockenbury, R.W.; Phillips, M.A.

1982-01-01

An integrated reliability analysis program combining graphic representation of fault trees, automated data base loadings and reference, and automated construction of reliability code input files was developed. The functional specifications for CADRIGS, the computer aided design reliability interactive graphics system, are presented. Previously developed fault tree segments used in auxiliary feedwater system safety analysis were constructed on CADRIGS and, when combined, yielded results identical to those resulting from manual input to the same reliability codes

Design and application of remote file management system

International Nuclear Information System (INIS)

Zhu Haijun; Liu Dekang; Shen liren

2006-01-01

File transfer protocol can help users transfer files between computers on internet. FTP can not fulfill the needs of users in special occasions, so it needs programmer define file transfer protocol himself based on users. The method or realization and application for user-defined file transfer protocol is introduced. (authors)

WSRC approach to validation of criticality safety computer codes

International Nuclear Information System (INIS)

Finch, D.R.; Mincey, J.F.

1991-01-01

Recent hardware and operating system changes at Westinghouse Savannah River Site (WSRC) have necessitated review of the validation for JOSHUA criticality safety computer codes. As part of the planning for this effort, a policy for validation of JOSHUA and other criticality safety codes has been developed. This policy will be illustrated with the steps being taken at WSRC. The objective in validating a specific computational method is to reliably correlate its calculated neutron multiplication factor (K eff ) with known values over a well-defined set of neutronic conditions. Said another way, such correlations should be: (1) repeatable; (2) demonstrated with defined confidence; and (3) identify the range of neutronic conditions (area of applicability) for which the correlations are valid. The general approach to validation of computational methods at WSRC must encompass a large number of diverse types of fissile material processes in different operations. Special problems are presented in validating computational methods when very few experiments are available (such as for enriched uranium systems with principal second isotope 236 U). To cover all process conditions at WSRC, a broad validation approach has been used. Broad validation is based upon calculation of many experiments to span all possible ranges of reflection, nuclide concentrations, moderation ratios, etc. Narrow validation, in comparison, relies on calculations of a few experiments very near anticipated worst-case process conditions. The methods and problems of broad validation are discussed

Calculations of reactor-accident consequences, Version 2. CRAC2: computer code user's guide

International Nuclear Information System (INIS)

Ritchie, L.T.; Johnson, J.D.; Blond, R.M.

1983-02-01

The CRAC2 computer code is a revision of the Calculation of Reactor Accident Consequences computer code, CRAC, developed for the Reactor Safety Study. The CRAC2 computer code incorporates significant modeling improvements in the areas of weather sequence sampling and emergency response, and refinements to the plume rise, atmospheric dispersion, and wet deposition models. New output capabilities have also been added. This guide is to facilitate the informed and intelligent use of CRAC2. It includes descriptions of the input data, the output results, the file structures, control information, and five sample problems

40 CFR 716.25 - Adequate file search.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 30 2010-07-01 2010-07-01 false Adequate file search. 716.25 Section... ACT HEALTH AND SAFETY DATA REPORTING General Provisions § 716.25 Adequate file search. The scope of a person's responsibility to search records is limited to records in the location(s) where the required...

A computer controlled tele-cobalt unit

International Nuclear Information System (INIS)

Brace, J.A.

1982-01-01

A computer controlled cobalt treatment unit was commissioned for treating patients in January 1980. Initially the controlling computer was a minicomputer, but now the control of the therapy unit is by a microcomputer. The treatment files, which specify the movement and configurations necessary to deliver the prescribed dose, are produced on the minicomputer and then transferred to the microcomputer using minitape cartridges. The actual treatment unit is based on a standard cobalt unit with a few additional features e.g. the drive motors can be controlled either by the computer or manually. Since the treatment unit is used for both manual and automatic treatments, the operational procedure under computer control is made to closely follow the manual procedure for a single field treatment. The necessary safety features which protect against human, hardware and software errors as well as the advantages and disadvantages of computer controlled radiotherapy are discussed

A Computational Framework for Flood Risk Assessment in The Netherlands

Directory of Open Access Journals (Sweden)

A.A. Markus

2010-01-01

Full Text Available The safety of dikes in The Netherlands, located in the delta of the rivers Rhine, Meuse and Scheldt, has been the subject of debate for more than ten years. The safety (or flood risk of a particular area may depend on the safety of other areas. This is referred to as effects of river system behaviour on flood risk (quantified as the estimated number of casualties and economic damage. A computational framework was developed to assess these effects. It consists of several components that are loosely coupled via data files and Tcl scripts to manage the individual programs and keep track of the state of the computations. The computations involved are lengthy (days or even weeks on a Linux cluster, which makes the framework currently more suitable for planning and design than for real-time operation. While the framework was constructed ad hoc, it can also be viewed more formally as a tuplespace Realising this makes it possible to adopt the philosophy for other similar frameworks.

Comparative evaluation of effect of rotary and reciprocating single-file systems on pericervical dentin: A cone-beam computed tomography study.

Science.gov (United States)

Zinge, Priyanka Ramdas; Patil, Jayaprakash

2017-01-01

The aim of this study is to evaluate and compare the effect of one shape, Neolix rotary single-file systems and WaveOne, Reciproc reciprocating single-file systems on pericervical dentin (PCD) using cone-beam computed tomography (CBCT). A total of 40 freshly extracted mandibular premolars were collected and divided into two groups, namely, Group A - Rotary: A 1 - Neolix and A 2 - OneShape and Group B - Reciprocating: B 1 - WaveOne and B 2 - Reciproc. Preoperative scans of each were taken followed by conventional access cavity preparation and working length determination with 10-k file. Instrumentation of the canal was done according to the respective file system, and postinstrumentation CBCT scans of teeth were obtained. 90 μm thick slices were obtained 4 mm apical and coronal to the cementoenamel junction. The PCD thickness was calculated as the shortest distance from the canal outline to the closest adjacent root surface, which was measured in four surfaces, i.e., facial, lingual, mesial, and distal for all the groups in the two obtained scans. There was no significant difference found between rotary single-file systems and reciprocating single-file systems in their effect on PCD, but in Group B 2 , there was most significant loss of tooth structure in the mesial, lingual, and distal surface ( P file system removes more PCD as compared to other experimental groups, whereas Neolix single file system had the least effect on PCD.

A Centralized Control and Dynamic Dispatch Architecture for File Integrity Analysis

Directory of Open Access Journals (Sweden)

Ronald DeMara

2006-02-01

Full Text Available The ability to monitor computer file systems for unauthorized changes is a powerful administrative tool. Ideally this task could be performed remotely under the direction of the administrator to allow on-demand checking, and use of tailorable reporting and exception policies targeted to adjustable groups of network elements. This paper introduces M-FICA, a Mobile File Integrity and Consistency Analyzer as a prototype to achieve this capability using mobile agents. The M-FICA file tampering detection approach uses MD5 message digests to identify file changes. Two agent types, Initiator and Examiner, are used to perform file integrity tasks. An Initiator travels to client systems, computes a file digest, then stores those digests in a database file located on write-once media. An Examiner agent computes a new digest to compare with the original digests in the database file. Changes in digest values indicate that the file contents have been modified. The design and evaluation results for a prototype developed in the Concordia agent framework are described.

28 CFR 32.32 - Time for filing claim.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 1 2010-07-01 2010-07-01 false Time for filing claim. 32.32 Section 32.32 Judicial Administration DEPARTMENT OF JUSTICE PUBLIC SAFETY OFFICERS' DEATH, DISABILITY, AND EDUCATIONAL ASSISTANCE BENEFIT CLAIMS Educational Assistance Benefit Claims § 32.32 Time for filing claim. (a...

Enhanced operational safety of BWRs by advanced computer technology and human engineering

International Nuclear Information System (INIS)

Tomizawa, T.; Fukumoto, A.; Neda, T.; Toda, Y.; Takizawa, Y.

1984-01-01

In BWR nuclear power plants, where unit capacity is increasing and the demand for assured safety is growing, it has become important for the information interface between man and machine to work smoothly. Efforts to improve man-machine communication have been going on for the past ten years in Japan. Computer facilities and colour CRT display systems are amongst the most useful new methods. Advanced computer technology has been applied to operating plants and found to be very helpful for safe operation. A display monitoring system (DMS) is in operation in a 1100 MW(e) BWR plant. A total combination test was successfully completed on the 'plant operation by displayed information and automation' system (PODIA) in February 1983 before shipment to the site. The objective of this test was to verify the improved qualification of the newly developed advanced PODIA man-machine system by this enlarged fabrication test concept. In addition, the development of special graphics displays for the main control room and technical support centre to assist operators in assessing plant safety and diagnosing problems is required to meet post-TMI regulations. For this purpose, a prototype safety parameter display system (called Toshiba SPDS) with two colour CRT displays and a computer (TOSBAC-7/70) was developed in 1981 as an independent safety monitoring system. The PODIA and SPDS are now independent systems, but their combination has been found to be more useful and valuable for nuclear power plant safety. The paper discusses supervisory and operational concepts in the advanced main control room including SPDS, and describes the PODIA and SPDS verification tests including the valuable experience obtained after improvements in the qualification of these systems had been made to satisfactory operational safety levels. (author)

Method for quantitative assessment of nuclear safety computer codes

International Nuclear Information System (INIS)

Dearien, J.A.; Davis, C.B.; Matthews, L.J.

1979-01-01

A procedure has been developed for the quantitative assessment of nuclear safety computer codes and tested by comparison of RELAP4/MOD6 predictions with results from two Semiscale tests. This paper describes the developed procedure, the application of the procedure to the Semiscale tests, and the results obtained from the comparison

The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

Energy Technology Data Exchange (ETDEWEB)

Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

2006-07-01

The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

CINDA 83 (1977-1983). The index to literature and computer files on microscopic neutron data

International Nuclear Information System (INIS)

1983-01-01

CINDA, the Computer Index of Neutron Data, contains bibliographical references to measurements, calculations, reviews and evaluations of neutron cross-sections and other microscopic neutron data; it includes also index references to computer libraries of numerical neutron data exchanged between four regional neutron data centres. The present issue, CINDA 83, is an index to the literature on neutron data published after 1976. The basic volume, CINDA-A, together with the present issue, contains the full CINDA file as of 1 April 1983. A supplement to CINDA 83 is foreseen for fall 1983. Next year's issue, which is envisaged to be published in June 1984, will again cover all relevant literature that has appeared after 1976

Modification to the Monte Carlo N-Particle (MCNP) Visual Editor (MCNPVised) to Read in Computer Aided Design (CAD) Files

International Nuclear Information System (INIS)

Randolph Schwarz; Leland L. Carter; Alysia Schwarz

2005-01-01

Monte Carlo N-Particle Transport Code (MCNP) is the code of choice for doing complex neutron/photon/electron transport calculations for the nuclear industry and research institutions. The Visual Editor for Monte Carlo N-Particle is internationally recognized as the best code for visually creating and graphically displaying input files for MCNP. The work performed in this grant was used to enhance the capabilities of the MCNP Visual Editor to allow it to read in both 2D and 3D Computer Aided Design (CAD) files, allowing the user to electronically generate a valid MCNP input geometry

30 CFR 44.10 - Filing of petition; service.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Filing of petition; service. 44.10 Section 44... ADMINISTRATIVE REQUIREMENTS RULES OF PRACTICE FOR PETITIONS FOR MODIFICATION OF MANDATORY SAFETY STANDARDS Initial Procedure for Petitions for Modification § 44.10 Filing of petition; service. A petition for...

Role of computers in quality assurance in the LLL Criticality Safety Program

International Nuclear Information System (INIS)

Koponen, B.L.

1978-01-01

Some of the aspects of computational criticality safety quality assurance that have been emphasized in recent years at LLL are summarized. In particular, computer code changes that have been made that help the criticality analyst reduce the number of errors that he makes and to locate those that he does make; and how a computerized ''benchmark'' data base aids him in the validation of his computational methods are discussed

Dynamic Non-Hierarchical File Systems for Exascale Storage

Energy Technology Data Exchange (ETDEWEB)

Long, Darrell E. [Univ. of California, Santa Cruz, CA (United States); Miller, Ethan L [Univ. of California, Santa Cruz, CA (United States)

2015-02-24

This constitutes the final report for “Dynamic Non-Hierarchical File Systems for Exascale Storage”. The ultimate goal of this project was to improve data management in scientific computing and high-end computing (HEC) applications, and to achieve this goal we proposed: to develop the first, HEC-targeted, file system featuring rich metadata and provenance collection, extreme scalability, and future storage hardware integration as core design goals, and to evaluate and develop a flexible non-hierarchical file system interface suitable for providing more powerful and intuitive data management interfaces to HEC and scientific computing users. Data management is swiftly becoming a serious problem in the scientific community – while copious amounts of data are good for obtaining results, finding the right data is often daunting and sometimes impossible. Scientists participating in a Department of Energy workshop noted that most of their time was spent “...finding, processing, organizing, and moving data and it’s going to get much worse”. Scientists should not be forced to become data mining experts in order to retrieve the data they want, nor should they be expected to remember the naming convention they used several years ago for a set of experiments they now wish to revisit. Ideally, locating the data you need would be as easy as browsing the web. Unfortunately, existing data management approaches are usually based on hierarchical naming, a 40 year-old technology designed to manage thousands of files, not exabytes of data. Today’s systems do not take advantage of the rich array of metadata that current high-end computing (HEC) file systems can gather, including content-based metadata and provenance1 information. As a result, current metadata search approaches are typically ad hoc and often work by providing a parallel management system to the “main” file system, as is done in Linux (the locate utility), personal computers, and enterprise search

Current algorithms used in reactor safety codes and the impact of future computer development on these algorithms

International Nuclear Information System (INIS)

Mahaffy, J.H.; Liles, D.R.; Woodruff, S.B.

1985-01-01

Computational methods and solution procedures used in the US Nuclear Regulatory Commission's reactor safety systems codes, Transient Reactor Analysis Code (TRAC) and Reactor Leak and Power Safety Excursion Code (RELAP), are reviewed. Methods used in TRAC-PF1/MOD1, including the stability-enhancing two-step (SETS) technique, which permits fast computations by allowing time steps larger than the material Courant stability limit, are described in detail, and the differences from RELAP5/MOD2 are noted. Developments in computing, including parallel and vector processing, and their applicability to nuclear reactor safety codes are described. These developments, coupled with appropriate numerical methods, make detailed faster-than-real-time reactor safety analysis a realistic near-term possibility

Portable File Format (PFF) specifications

Energy Technology Data Exchange (ETDEWEB)

Dolan, Daniel H. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-02-01

Created at Sandia National Laboratories, the Portable File Format (PFF) allows binary data transfer across computer platforms. Although this capability is supported by many other formats, PFF files are still in use at Sandia, particularly in pulsed power research. This report provides detailed PFF specifications for accessing data without relying on legacy code.

F2AC: A Lightweight, Fine-Grained, and Flexible Access Control Scheme for File Storage in Mobile Cloud Computing

Directory of Open Access Journals (Sweden)

Wei Ren

2016-01-01

Full Text Available Current file storage service models for cloud servers assume that users either belong to single layer with different privileges or cannot authorize privileges iteratively. Thus, the access control is not fine-grained and flexible. Besides, most access control methods at cloud servers mainly rely on computationally intensive cryptographic algorithms and, especially, may not be able to support highly dynamic ad hoc groups with addition and removal of group members. In this paper, we propose a scheme called F2AC, which is a lightweight, fine-grained, and flexible access control scheme for file storage in mobile cloud computing. F2AC can not only achieve iterative authorization, authentication with tailored policies, and access control for dynamically changing accessing groups, but also provide access privilege transition and revocation. A new access control model called directed tree with linked leaf model is proposed for further implementations in data structures and algorithms. The extensive analysis is given for justifying the soundness and completeness of F2AC.

Computational Methods for Sensitivity and Uncertainty Analysis in Criticality Safety

International Nuclear Information System (INIS)

Broadhead, B.L.; Childs, R.L.; Rearden, B.T.

1999-01-01

Interest in the sensitivity methods that were developed and widely used in the 1970s (the FORSS methodology at ORNL among others) has increased recently as a result of potential use in the area of criticality safety data validation procedures to define computational bias, uncertainties and area(s) of applicability. Functional forms of the resulting sensitivity coefficients can be used as formal parameters in the determination of applicability of benchmark experiments to their corresponding industrial application areas. In order for these techniques to be generally useful to the criticality safety practitioner, the procedures governing their use had to be updated and simplified. This paper will describe the resulting sensitivity analysis tools that have been generated for potential use by the criticality safety community

Analytical methodology for safety validation of computer controlled subsystems. Volume 1 : state-of-the-art and assessment of safety verification/validation methodologies

Science.gov (United States)

1995-09-01

This report describes the development of a methodology designed to assure that a sufficiently high level of safety is achieved and maintained in computer-based systems which perform safety critical functions in high-speed rail or magnetic levitation ...

Computational system to create an entry file for replicating I-125 seeds simulating brachytherapy case studies using the MCNPX code

Directory of Open Access Journals (Sweden)

Leonardo da Silva Boia

2014-03-01

Full Text Available Purpose: A computational system was developed for this paper in the C++ programming language, to create a 125I radioactive seed entry file, based on the positioning of a virtual grid (template in voxel geometries, with the purpose of performing prostate cancer treatment simulations using the MCNPX code.Methods: The system is fed with information from the planning system with regard to each seed’s location and its depth, and an entry file is automatically created with all the cards (instructions for each seed regarding their cell blocks and surfaces spread out spatially in the 3D environment. The system provides with precision a reproduction of the clinical scenario for the MCNPX code’s simulation environment, thereby allowing the technique’s in-depth study.Results and Conclusion: The preliminary results from this study showed that the lateral penumbra of uniform scanning proton beams was less sensitive In order to validate the computational system, an entry file was created with 88 125I seeds that were inserted in the phantom’s MAX06 prostate region with initial activity determined for the seeds at the 0.27 mCi value. Isodose curves were obtained in all the prostate slices in 5 mm steps in the 7 to 10 cm interval, totaling 7 slices. Variance reduction techniques were applied in order to optimize computational time and the reduction of uncertainties such as photon and electron energy interruptions in 4 keV and forced collisions regarding cells of interest. Through the acquisition of isodose curves, the results obtained show that hot spots have values above 300 Gy, as anticipated in literature, stressing the importance of the sources’ correct positioning, in which the computational system developed provides, in order not to release excessive doses in adjacent risk organs. The 144 Gy prescription curve showed in the validation process that it covers perfectly a large percentage of the volume, at the same time that it demonstrates a large

Adding Data Management Services to Parallel File Systems

Energy Technology Data Exchange (ETDEWEB)

Brandt, Scott [Univ. of California, Santa Cruz, CA (United States)

2015-03-04

The objective of this project, called DAMASC for “Data Management in Scientific Computing”, is to coalesce data management with parallel file system management to present a declarative interface to scientists for managing, querying, and analyzing extremely large data sets efficiently and predictably. Managing extremely large data sets is a key challenge of exascale computing. The overhead, energy, and cost of moving massive volumes of data demand designs where computation is close to storage. In current architectures, compute/analysis clusters access data in a physically separate parallel file system and largely leave it scientist to reduce data movement. Over the past decades the high-end computing community has adopted middleware with multiple layers of abstractions and specialized file formats such as NetCDF-4 and HDF5. These abstractions provide a limited set of high-level data processing functions, but have inherent functionality and performance limitations: middleware that provides access to the highly structured contents of scientific data files stored in the (unstructured) file systems can only optimize to the extent that file system interfaces permit; the highly structured formats of these files often impedes native file system performance optimizations. We are developing Damasc, an enhanced high-performance file system with native rich data management services. Damasc will enable efficient queries and updates over files stored in their native byte-stream format while retaining the inherent performance of file system data storage via declarative queries and updates over views of underlying files. Damasc has four key benefits for the development of data-intensive scientific code: (1) applications can use important data-management services, such as declarative queries, views, and provenance tracking, that are currently available only within database systems; (2) the use of these services becomes easier, as they are provided within a familiar file

Schools (Students) Exchanging CAD/CAM Files over the Internet.

Science.gov (United States)

Mahoney, Gary S.; Smallwood, James E.

This document discusses how students and schools can benefit from exchanging computer-aided design/computer-aided manufacturing (CAD/CAM) files over the Internet, explains how files are exchanged, and examines the problem of selected hardware/software incompatibility. Key terms associated with information search services are defined, and several…

Computerized index for teaching files

International Nuclear Information System (INIS)

Bramble, J.M.

1989-01-01

A computerized index can be used to retrieve cases from a teaching file that have radiographic findings similar to an unknown case. The probability that a user will review cases with a correct diagnosis was estimated with use of radiographic findings of arthritis in hand radiographs of 110 cases from a teaching file. The nearest-neighbor classification algorithm was used as a computer index to 110 cases of arthritis. Each case was treated as an unknown and inputted to the computer index. The accuracy of the computer index in retrieving cases with the same diagnosis (including rheumatoid arthritis, gout, psoriatic arthritis, inflammatory osteoarthritis, and pyrophosphate arthropathy) was measured. A Bayes classifier algorithm was also tested on the same database. Results are presented. The nearest-neighbor algorithm was 83%. By comparison, the estimated accuracy of the Bayes classifier algorithm was 78%. Conclusions: A computerized index to a teaching file based on the nearest-neighbor algorithm should allow the user to review cases with the correct diagnosis of an unknown case, by entering the findings of the unknown case

Securing the AliEn File Catalogue - Enforcing authorization with accountable file operations

International Nuclear Information System (INIS)

Schreiner, Steffen; Banerjee, Subho Sankar; Betev, Latchezar; Carminati, Federico; Vladimirovna Datskova, Olga; Furano, Fabrizio; Grigoras, Alina; Grigoras, Costin; Mendez Lorenzo, Patricia; Peters, Andreas Joachim; Saiz, Pablo; Bagnasco, Stefano; Zhu Jianlin

2011-01-01

The AliEn Grid Services, as operated by the ALICE Collaboration in its global physics analysis grid framework, is based on a central File Catalogue together with a distributed set of storage systems and the possibility to register links to external data resources. This paper describes several identified vulnerabilities in the AliEn File Catalogue access protocol regarding fraud and unauthorized file alteration and presents a more secure and revised design: a new mechanism, called LFN Booking Table, is introduced in order to keep track of access authorization in the transient state of files entering or leaving the File Catalogue. Due to a simplification of the original Access Envelope mechanism for xrootd-protocol-based storage systems, fundamental computational improvements of the mechanism were achieved as well as an up to 50% reduction of the credential's size. By extending the access protocol with signed status messages from the underlying storage system, the File Catalogue receives trusted information about a file's size and checksum and the protocol is no longer dependent on client trust. Altogether, the revised design complies with atomic and consistent transactions and allows for accountable, authentic, and traceable file operations. This paper describes these changes as part and beyond the development of AliEn version 2.19.

LIMBO computer code for analyzing coolant-voiding dynamics in LMFBR safety tests

International Nuclear Information System (INIS)

Bordner, G.L.

1979-10-01

The LIMBO (liquid metal boiling) code for the analysis of two-phase flow phenomena in an LMFBR reactor coolant channel is presented. The code uses a nonequilibrium, annular, two-phase flow model, which allows for slip between the phases. Furthermore, the model is intended to be valid for both quasi-steady boiling and rapid coolant voiding of the channel. The code was developed primarily for the prediction of, and the posttest analysis of, coolant-voiding behavior in the SLSF P-series in-pile safety test experiments. The program was conceived to be simple, efficient, and easy to use. It is particularly suited for parametric studies requiring many computer runs and for the evaluation of the effects of model or correlation changes that require modification of the computer program. The LIMBO code, of course, lacks the sophistication and model detail of the reactor safety codes, such as SAS, and is therefore intended to compliment these safety codes

Zebra: A striped network file system

Science.gov (United States)

Hartman, John H.; Ousterhout, John K.

1992-01-01

The design of Zebra, a striped network file system, is presented. Zebra applies ideas from log-structured file system (LFS) and RAID research to network file systems, resulting in a network file system that has scalable performance, uses its servers efficiently even when its applications are using small files, and provides high availability. Zebra stripes file data across multiple servers, so that the file transfer rate is not limited by the performance of a single server. High availability is achieved by maintaining parity information for the file system. If a server fails its contents can be reconstructed using the contents of the remaining servers and the parity information. Zebra differs from existing striped file systems in the way it stripes file data: Zebra does not stripe on a per-file basis; instead it stripes the stream of bytes written by each client. Clients write to the servers in units called stripe fragments, which are analogous to segments in an LFS. Stripe fragments contain file blocks that were written recently, without regard to which file they belong. This method of striping has numerous advantages over per-file striping, including increased server efficiency, efficient parity computation, and elimination of parity update.

Cone-beam Computed Tomographic Assessment of Canal Centering Ability and Transportation after Preparation with Twisted File and Bio RaCe Instrumentation.

Directory of Open Access Journals (Sweden)

Kiamars Honardar

2014-08-01

Full Text Available Use of rotary Nickel-Titanium (NiTi instruments for endodontic preparation has introduced a new era in endodontic practice, but this issue has undergone dramatic modifications in order to achieve improved shaping abilities. Cone-beam computed tomography (CBCT has made it possible to accurately evaluate geometrical changes following canal preparation. This study was carried out to compare canal centering ability and transportation of Twisted File and BioRaCe rotary systems by means of cone-beam computed tomography.Thirty root canals from freshly extracted mandibular and maxillary teeth were selected. Teeth were mounted and scanned before and after preparation by CBCT at different apical levels. Specimens were divided into 2 groups of 15. In the first group Twisted File and in the second, BioRaCe was used for canal preparation. Canal transportation and centering ability after preparation were assessed by NNT Viewer and Photoshop CS4 software. Statistical analysis was performed using t-test and two-way ANOVA.All samples showed deviations from the original axes of the canals. No significant differences were detected between the two rotary NiTi instruments for canal centering ability in all sections. Regarding canal transportation however, a significant difference was seen in the BioRaCe group at 7.5mm from the apex.Under the conditions of this in vitro study, Twisted File and BioRaCe rotary NiTi files retained original canal geometry.

Evaluation of clinical data in childhood asthma. Application of a computer file system

International Nuclear Information System (INIS)

Fife, D.; Twarog, F.J.; Geha, R.S.

1983-01-01

A computer file system was used in our pediatric allergy clinic to assess the value of chest roentgenograms and hemoglobin determinations used in the examination of patients and to correlate exposure to pets and forced hot air with the severity of asthma. Among 889 children with asthma, 20.7% had abnormal chest roentgenographic findings, excluding hyperinflation and peribronchial thickening, and 0.7% had abnormal hemoglobin values. Environmental exposure to pets or forced hot air was not associated with increased severity of asthma, as assessed by five measures of outcome: number of medications administered, requirement for corticosteroids, frequency of clinic visits, frequency of emergency room visits, and frequency of hospitalizations

The development of an information system and installation of an Internet web database for the purposes of the occupational health and safety management system.

Science.gov (United States)

Mavrikakis, I; Mantas, J; Diomidous, M

2007-01-01

This paper is based on the research on the possible structure of an information system for the purposes of occupational health and safety management. We initiated a questionnaire in order to find the possible interest on the part of potential users in the subject of occupational health and safety. The depiction of the potential interest is vital both for the software analysis cycle and development according to previous models. The evaluation of the results tends to create pilot applications among different enterprises. Documentation and process improvements ascertained quality of services, operational support, occupational health and safety advice are the basics of the above applications. Communication and codified information among intersted parts is the other target of the survey regarding health issues. Computer networks can offer such services. The network will consist of certain nodes responsible to inform executives on Occupational Health and Safety. A web database has been installed for inserting and searching documents. The submission of files to a server and the answers to questionnaires through the web help the experts to perform their activities. Based on the requirements of enterprises we have constructed a web file server. We submit files so that users can retrieve the files which they need. The access is limited to authorized users. Digital watermarks authenticate and protect digital objects.

ERX: a software for editing files containing X-ray spectra to be used in exposure computational models

International Nuclear Information System (INIS)

Cabral, Manuela O.M.; Vieira, Jose W.; Silva, Alysson G.; Leal Neto, Viriato; Oliveira, Alex C.H.; Lima, Fernando R.A.

2011-01-01

Exposure Computational Models (ECMs) are utilities that simulate situations in which occurs irradiation in a given environment. An ECM is composed primarily by an anthropomorphic model (phantom), and a Monte Carlo code (MC). This paper presents a tutorial of the software Espectro de Raios-X (ERX). This software performs reading and numerical and graphical analysis of text files containing diagnostic X-ray spectra for use in algorithms of radioactive sources in the ECMs of a Grupo de Dosimetria Numerica. The ERX allows the user to select one among several X-ray spectrums in the energy range Diagnostic radiology X-Ray most commonly used in radiology clinics. In the current version of the ERX there are two types of input files: the contained in mspectra.dat file and the resulting of MC simulations in Geant4. The software allows the construction of charts of the Probability Density Function (PDF) and Cumulative Distribution Function (CDF) of a selected spectrum as well as the table with the values of these functions and the spectrum. In addition, the ERX allows the user to make comparative analysis between the PDF graphics of the two catalogs of spectra available, besides being can perform dosimetric evaluations with the selected spectrum. A software of this kind is an important computational tool for researchers in numerical dosimetry because of the diversity of Diagnostic radiology X-Ray machines, which implies in a mass of input data highly diverse. And because of this, the ERX provides independence to the group related to the data origin that is contained in the catalogs created, not being necessary to resort to others. (author)

Reactor fuel performance data file, 1985 edition

International Nuclear Information System (INIS)

Harayama, Yasuo; Fujita, Misao; Watanabe, Kohji.

1986-07-01

In safety evaluation and integrity studies of reactor fuel, data on fuel performance are the most basic materials. The Fuel Reliability Laboratory No.1 has obtained the fuel performance data by joining in some international programs to study the safety and integrity of fuel. Those data have only used for the studies in the above two fields. However, if the data are rearranged and compiled in a easily usable form, they can be utilized in other field of studies. Then, a 'data file' on fuel performance is beeing compiled by adding data from open literatures to those obtained in international programs. The present report is prepared on the basis of the data file compiled by March in 1986. (author)

Computer-based systems important to safety (COMPSIS) - Reporting guidelines

International Nuclear Information System (INIS)

1999-07-01

The objective of this procedure is to help the user to prepare an COMPSIS report on an event so that important lessons learned are most efficiently transferred to the database. This procedure focuses on the content of the information to be provided in the report rather than on its format. The established procedure follows to large extend the procedure chosen by the IRS incident reporting system. However this database is built for I and C equipment with the purpose of the event report database to collect and disseminate information on events of significance involving Computer-Based Systems important to safety in nuclear power plants, and feedback conclusions and lessons learnt from such events. For events where human performance is dominant to draw lessons, more detailed guidance on the specific information that should be supplied is spelled out in the present procedure. This guidance differs somewhat from that for the provision of technical information, and takes into account that the engineering world is usually less familiar with human behavioural analysis than with technical analysis. The events to be reported to the COMPSIS database should be based on the national reporting criteria in the participating member countries. The aim is that all reports including computer based systems that meet each country reporting criteria should be reported. The database should give a broad picture of events/incidents occurring in operation with computer control systems. As soon as an event has been identified, the insights and lessons learnt to be conveyed to the international nuclear community shall be clearly identified. On the basis of the description of the event, the event shall be analyzed in detail under the aspect of direct and potential impact to plant safety functions. The first part should show the common involvement of operation and safety systems and the second part should show the special aspects of I and C functions, hardware and software

49 CFR 805.735-26 - Employee's complaint on filing requirements.

Science.gov (United States)

2010-10-01

...) NATIONAL TRANSPORTATION SAFETY BOARD EMPLOYEE RESPONSIBILITIES AND CONDUCT § 805.735-26 Employee's complaint on filing requirements. An employee who believes that his position has been improperly included... 49 Transportation 7 2010-10-01 2010-10-01 false Employee's complaint on filing requirements. 805...

Geothermal-energy files in computer storage: sites, cities, and industries

Energy Technology Data Exchange (ETDEWEB)

O' Dea, P.L.

1981-12-01

The site, city, and industrial files are described. The data presented are from the hydrothermal site file containing about three thousand records which describe some of the principal physical features of hydrothermal resources in the United States. Data elements include: latitude, longitude, township, range, section, surface temperature, subsurface temperature, the field potential, and well depth for commercialization. (MHR)

System and software safety analysis for the ERA control computer

International Nuclear Information System (INIS)

Beerthuizen, P.G.; Kruidhof, W.

2001-01-01

The European Robotic Arm (ERA) is a seven degrees of freedom relocatable anthropomorphic robotic manipulator system, to be used in manned space operation on the International Space Station, supporting the assembly and external servicing of the Russian segment. The safety design concept and implementation of the ERA is described, in particular with respect to the central computer's software design. A top-down analysis and specification process is used to down flow the safety aspects of the ERA system towards the subsystems, which are produced by a consortium of companies in many countries. The user requirements documents and the critical function list are the key documents in this process. Bottom-up analysis (FMECA) and test, on both subsystem and system level, are the basis for safety verification. A number of examples show the use of the approach and methods used

Summary report of the technical meeting on 'International Reactor Dosimetry File: IRDF-2002'

International Nuclear Information System (INIS)

Greenwood, L.R.; Paviotti-Corcuera, R.

2002-09-01

This report summarizes the presentations, recommendations and conclusions of the Technical Meeting on 'International Reactor Dosimetry File: IRDF-2002.' The purpose of this meeting was to discuss scientific and technical matters related to the subject and coordinate related tasks. Discussions were held and recommendations were given for the preparation of the files on topics related to: reactions to be included, need for new evaluations or revisions, decay data, radiation damage data, integral testing in benchmark fields, and computer codes to be included. Tasks were assigned and deadlines were set. The participants emphasized that accurate and complete knowledge of nuclear data for reactor dosimetry are essential for improving the accuracy of the reactor pressure vessel service life assessment of nuclear power plants as well as in other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. (author)

Safety integrity requirements for computer based I ampersand C systems

International Nuclear Information System (INIS)

Thuy, N.N.Q.; Ficheux-Vapne, F.

1997-01-01

In order to take into account increasingly demanding functional requirements, many instrumentation and control (I ampersand C) systems in nuclear power plants are implemented with computers. In order to ensure the required safety integrity of such equipment, i.e., to ensure that they satisfactorily perform the required safety functions under all stated conditions and within stated periods of time, requirements applicable to these equipment and to their life cycle need to be expressed and followed. On the other hand, the experience of the last years has led EDF (Electricite de France) and its partners to consider three classes of systems and equipment, according to their importance to safety. In the EPR project (European Pressurized water Reactor), these classes are labeled E1A, E1B and E2. The objective of this paper is to present the outline of the work currently done in the framework of the ETC-I (EPR Technical Code for I ampersand C) regarding safety integrity requirements applicable to each of the three classes. 4 refs., 2 figs

MR-AFS: a global hierarchical file-system

International Nuclear Information System (INIS)

Reuter, H.

2000-01-01

The next generation of fusion experiments will use object-oriented technology creating the need for world wide sharing of an underlying hierarchical file-system. The Andrew file system (AFS) is a well known and widely spread global distributed file-system. Multiple-resident-AFS (MR-AFS) combines the features of AFS with hierarchical storage management systems. Files in MR-AFS therefore may be migrated on secondary storage, such as roboted tape libraries. MR-AFS is in use at IPP for the current experiments and data originating from super-computer applications. Experiences and scalability issues are discussed

Access to DIII-D data located in multiple files and multiple locations

International Nuclear Information System (INIS)

McHarg, B.B. Jr.

1993-10-01

The General Atomics DIII-D tokamak fusion experiment is now collecting over 80 MB of data per discharge once every 10 min, and that quantity is expected to double within the next year. The size of the data files, even in compressed format, is becoming increasingly difficult to handle. Data is also being acquired now on a variety of UNIX systems as well as MicroVAX and MODCOMP computer systems. The existing computers collect all the data into a single shot file, and this data collection is taking an ever increasing amount of time as the total quantity of data increases. Data is not available to experimenters until it has been collected into the shot file, which is in conflict with the substantial need for data examination on a timely basis between shots. The experimenters are also spread over many different types of computer systems (possibly located at other sites). To improve data availability and handling, software has been developed to allow individual computer systems to create their own shot files locally. The data interface routine PTDATA that is used to access DIII-D data has been modified so that a user's code on any computer can access data from any computer where that data might be located. This data access is transparent to the user. Breaking up the shot file into separate files in multiple locations also impacts software used for data archiving, data management, and data restoration

Total system for manufacture of nuclear vessels by computer: VECTRON

International Nuclear Information System (INIS)

Inagawa, Jin; Ueno, Osamu; Hanai, Yoshiharu; Ohkawa, Isao; Washizu, Hideyuki

1980-01-01

VECTRON (Vessel Engineering by Computer Tool and Rapid Operating for the N/C System) is a CAM (Computer Aided Manufacturing) system that has been developed to produce high quality and highly accurate vessels for nuclear power plants and other industrial plants. Outputs of this system are design drawings, manufacturing information and magnetic tapes of the N/C marking machine for vessel shell plates including their attachments. And it can also output information at each stage of designing, marking, cutting, forming and assembling by treating the vessels in three dimensions and by using data filing systems and plotting program for general use. The data filing systems consist of functional and manufacturing data of each part of vessels. This system not only realizes a change from manual work to computer work, but also leads us to improve production engineering and production jigs for safety and high quality. At present, VECTRON is being applied to the manufacture of the shell plates of primary containment vessels in the Kashiwazaki-Kariwa Nuclear Power Station Unit 1 (K-1) and the Fukushima Daini Nuclear Power Station Unit 3 (2F-3), to realize increased productivity. (author)

Technical safety Organisations (TSO) contribute to European Nuclear Safety

International Nuclear Information System (INIS)

Repussard, J.

2010-01-01

Nuclear safety and radiation protection rely on science to achieve high level prevention objectives, through the analysis of safety files proposed by the licensees. The necessary expertise needs to be exercised so as to ensure adequate independence from nuclear operators, appropriate implementation of state of the art knowledge, and a broad spectrum of analysis, adequately ranking the positive and negative points of the safety files. The absence of a Europe-wide nuclear safety regime is extremely costly for an industry which has to cope with a highly competitive and open international environment, but has to comply with fragmented national regulatory systems. Harmonization is therefore critical, but such a goal is difficult to achieve. Only a gradual policy, made up of planned steps in each of the three key dimensions of the problem (energy policy at EU level, regulatory harmonization, consolidation of Europe-wide technical expertise capability) can be successful to achieve the required integration on the basis of the highest safety levels. TSO's contribute to this consolidation, with the support of the EC, in the fields of research (EURATOM-Programmes), of experience feedback analysis (European Clearinghouse), of training and knowledge management (European Training and Tutoring Institute, EUROSAFE). The TSO's network, ETSON, is becoming a formal organisation, able to enter into formal dialogue with EU institutions. However, nuclear safety nevertheless remains a world wide issue, requiring intensive international cooperation, including on TSO issues. (author)

The NUSS safety guides in design and the use of computers

International Nuclear Information System (INIS)

Fischer, J.

1986-01-01

After a brief summary of the NUSS programme, the two design guides are discussed which deal with instrumentation and control circuitry. The potential use of computers is covered differently in these guides because of the historical development and more importantly because of the difference in importance to safety of the I and C systems which are dealt with in these papers. The Agency would consider modifications to the existing guides only when sufficient consensus about the use of computers would warrant a revision of the documents. (author)

Computer-assisted navigational surgery enhances safety in dental implantology.

Science.gov (United States)

Ng, F C; Ho, K H; Wexler, A

2005-06-01

Dental implants are increasingly used to restore missing dentition. These titanium implants are surgically installed in the edentulous alveolar ridge and allowed to osteointegrate with the bone during the healing phase. After osseo-integration, the implant is loaded with a prosthesis to replace the missing tooth. Conventional implant treatment planning uses study models, wax-ups and panoramic x-rays to prefabricate surgical stent to guide the preparation of the implant site. The drilling into the alveolar ridge is invariably a "blind" procedure as the part of the drill in bone is not visible. Stereotactic systems were first introduced into neurosurgery in 1986. Since then, computer-assisted navigational technology has brought major advances to neuro-, midface and orthopaedic surgeries, and more recently, to implant placement. This paper illustrates the use of real-time computer-guided navigational technology in enhancing safety in implant surgical procedures. Real-time computer-guided navigational technology enhances accuracy and precision of the surgical procedure, minimises complications and facilitates surgery in challenging anatomical locations.

JNDC FP decay data file

International Nuclear Information System (INIS)

Yamamoto, Tohru; Akiyama, Masatsugu

1981-02-01

The decay data file for fission product nuclides (FP DECAY DATA FILE) has been prepared for summation calculation of the decay heat of fission products. The average energies released in β- and γ-transitions have been calculated with computer code PROFP. The calculated results and necessary information have been arranged in tabular form together with the estimated results for 470 nuclides of which decay data are not available experimentally. (author)

The SCALE Web site: Resources for the worldwide nuclear criticality safety community

International Nuclear Information System (INIS)

Bowman, S.M.

2000-01-01

The Standardized Computer Analyses for Licensing Evaluations (SCALE) computer software system developed at Oak Ridge National Laboratory (ORNL) is widely used and accepted around the world for criticality safety analyses. SCALE includes the well-known KENO V.a and KENO VI three-dimensional Monte Carlo criticality computer codes. For several years, the SCALE staff at ORNL has maintained a Web site to provide information and support to sponsors and users in the worldwide criticality safety community. The SCALE WEB site is located at www.cped.ornl.gov/scale and provides information in the following areas: 1. important notices to users; 2. SCALE Users Electronic Notebook; 3. current and past issues of the SCALE Newsletter; 4. verification and validation (V and V) and benchmark reports; 5. download updates, utilities, and V and V input files; 6. SCALE training course information; 7. SCALE Manual on-line; 8. overview of SCALE system; 9. how to install and run SCALE; 10. SCALE quality assurance documents; and 11. nuclear resources on the Internet

77 FR 50723 - Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety...

Science.gov (United States)

2012-08-22

... regulations with respect to software verification and auditing of digital computer software used in the safety... Standards and Records,'' which requires, in part, that a quality assurance program be established and implemented to provide adequate assurance that systems and components important to safety will satisfactorily...

Database structure and file layout of Nuclear Power Plant Database. Database for design information on Light Water Reactors in Japan

International Nuclear Information System (INIS)

Yamamoto, Nobuo; Izumi, Fumio.

1995-12-01

The Nuclear Power Plant Database (PPD) has been developed at the Japan Atomic Energy Research Institute (JAERI) to provide plant design information on domestic Light Water Reactors (LWRs) to be used for nuclear safety research and so forth. This database can run on the main frame computer in the JAERI Tokai Establishment. The PPD contains the information on the plant design concepts, the numbers, capacities, materials, structures and types of equipment and components, etc, based on the safety analysis reports of the domestic LWRs. This report describes the details of the PPD focusing on the database structure and layout of data files so that the users can utilize it efficiently. (author)

File-System Workload on a Scientific Multiprocessor

Science.gov (United States)

Kotz, David; Nieuwejaar, Nils

1995-01-01

Many scientific applications have intense computational and I/O requirements. Although multiprocessors have permitted astounding increases in computational performance, the formidable I/O needs of these applications cannot be met by current multiprocessors a their I/O subsystems. To prevent I/O subsystems from forever bottlenecking multiprocessors and limiting the range of feasible applications, new I/O subsystems must be designed. The successful design of computer systems (both hardware and software) depends on a thorough understanding of their intended use. A system designer optimizes the policies and mechanisms for the cases expected to most common in the user's workload. In the case of multiprocessor file systems, however, designers have been forced to build file systems based only on speculation about how they would be used, extrapolating from file-system characterizations of general-purpose workloads on uniprocessor and distributed systems or scientific workloads on vector supercomputers (see sidebar on related work). To help these system designers, in June 1993 we began the Charisma Project, so named because the project sought to characterize 1/0 in scientific multiprocessor applications from a variety of production parallel computing platforms and sites. The Charisma project is unique in recording individual read and write requests-in live, multiprogramming, parallel workloads (rather than from selected or nonparallel applications). In this article, we present the first results from the project: a characterization of the file-system workload an iPSC/860 multiprocessor running production, parallel scientific applications at NASA's Ames Research Center.

Super analog computer for evaluating the safety of buried radioactive waste

International Nuclear Information System (INIS)

Cohen, B.L.

1980-01-01

It is argued that the past use of digital computer programs for evaluating the safety of buried radioactive waste has been largely wasteful and dangerously delusive. It is suggested to use actual rocks as the analog of buried waste. The problem of comparable rates of leaching of radioactive waste and of natural rock is discussed. Two examples are given of the use of natural rock as an ''analog computer'': one for high-level radioactive waste, and one for low-level radioactive waste. Digital computers have not contributed anything to two crucial questions: Can shafts be securely sealed. Does the heat crack the rock or have important effects on its chemistry. 4 refs

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Intercomparison and validation of computer codes for thermalhydraulic safety analysis of heavy water reactors

International Nuclear Information System (INIS)

2004-08-01

Activities within the frame of the IAEA's Technical Working Group on Advanced Technologies for HWRs (TWG-HWR) are conducted in a project within the IAEA's subprogramme on nuclear power reactor technology development. The objective of the activities on HWRs is to foster, within the frame of the TWG-HWR, information exchange and co-operative research on technology development for current and future HWRs, with an emphasis on safety, economics and fuel resource sustainability. One of the activities recommended by the TWG-HWR was an international standard problem exercise entitled: Intercomparison and validation of computer codes for thermalhydraulics safety analyses. Intercomparison and validation of computer codes used in different countries for thermalhydraulics safety analyses will enhance the confidence in the predictions made by these codes. However, the intercomparison and validation exercise needs a set of reliable experimental data. The RD-14M Large-Loss Of Coolant Accident (LOCA) test B9401 simulating HWR LOCA behaviour that was conducted by Atomic Energy of Canada Ltd (AECL) was selected for this validation project. This report provides a comparison of the results obtained from six participating countries, utilizing four different computer codes. General conclusions are reached and recommendations made

Evaluation of Single File Systems Reciproc, Oneshape, and WaveOne using Cone Beam Computed Tomography -An In Vitro Study.

Science.gov (United States)

Dhingra, Annil; Ruhal, Nidhi; Miglani, Anjali

2015-04-01

Successful endodontic therapy depends on many factor, one of the most important step in any root canal treatment is root canal preparation. In addition, respecting the original shape of the canal is of the same importance; otherwise, canal aberrations such as transportation will be created. The purpose of this study is to compare and evaluate Reciprocating WaveOne ,Reciproc and Rotary Oneshape Single File Instrumentation System On Cervical Dentin Thickness, Cross Sectional Area and Canal Transportation on First Mandibular Molar Using Cone Beam Computed Tomography. Sixty Mandibular First Molars extracted due to periodontal reason was collected from the Department of Oral and Maxillofacial. Teeth were prepared using one rotary and two reciprocating single file system. Teeth were divided into 3 groups 20 teeth in each group. Pre instrumentation and Post instrumentation scans was done and evaluated for three parameters Canal Transportation, Cervical Dentinal Thickness, Cross-sectional Area. Results were analysed statistically using ANOVA, Post-Hoc Tukey analysis. The change in cross-sectional area after filing showed significant difference at 0mm, 1mm, 2mm and 7mm (pfile system over a distance of 7 mm (starting from 0mm and then evaluation at 1mm, 2mm, 3mm, 5mm and 7mm), the results showed a significant difference among the file systems at various lengths (p= 0.014, 0.046, 0.004, 0.028, 0.005 & 0.029 respectively). Mean value of cervical dentinal removal is maximum at all the levels for oneshape and minimum for waveone showing the better quality of waveone and reciproc over oneshape file system. Significant difference was found at 9mm, 11mm and 12mm between all the three file systems (p<0.001,< 0.001, <0.001). It was concluded that reciprocating motion is better than rotary motion in all the three parameters Canal Transportation, Cross-sectional Area, Cervical Dentinal Thickness.

Distributed Data Management and Distributed File Systems

CERN Document Server

Girone, Maria

2015-01-01

The LHC program has been successful in part due to the globally distributed computing resources used for collecting, serving, processing, and analyzing the large LHC datasets. The introduction of distributed computing early in the LHC program spawned the development of new technologies and techniques to synchronize information and data between physically separated computing centers. Two of the most challenges services are the distributed file systems and the distributed data management systems. In this paper I will discuss how we have evolved from local site services to more globally independent services in the areas of distributed file systems and data management and how these capabilities may continue to evolve into the future. I will address the design choices, the motivations, and the future evolution of the computing systems used for High Energy Physics.

Methods and Algorithms for Detecting Objects in Video Files

Directory of Open Access Journals (Sweden)

Nguyen The Cuong

2018-01-01

Full Text Available Video files are files that store motion pictures and sounds like in real life. In today's world, the need for automated processing of information in video files is increasing. Automated processing of information has a wide range of application including office/home surveillance cameras, traffic control, sports applications, remote object detection, and others. In particular, detection and tracking of object movement in video file plays an important role. This article describes the methods of detecting objects in video files. Today, this problem in the field of computer vision is being studied worldwide.

76 FR 81761 - Mine Safety Disclosure

Science.gov (United States)

2011-12-28

... or other mine to file a current report on Form 8-K with the Commission reporting receipt of certain....\\24\\ Issuers have been providing disclosure in their periodic and current reports filed with the... Release, that to the extent mine safety issues are material, under our current rules disclosure could be...

Three computer codes for safety and stability of large superconducting magnets

International Nuclear Information System (INIS)

Turner, L.R.

1985-01-01

For analyzing the safety and stability of large superconducting magnets, three computer codes TASS, SHORTURN, and SSICC have been developed, applicable to bath-cooled magnets, bath-cooled magnets with shorted turns, and magnets with internally cooled conductors respectively. The TASS code is described, and the use of the three codes is reviewed

Computer program for storage of historical and routine safety data related to radiologically controlled facilities

International Nuclear Information System (INIS)

Marsh, D.A.; Hall, C.J.

1984-01-01

A method for tracking and quick retrieval of radiological status of radiation and industrial safety systems in an active or inactive facility has been developed. The system uses a mini computer, a graphics plotter, and mass storage devices. Software has been developed which allows input and storage of architectural details, radiological conditions such as exposure rates, current location of safety systems, and routine and historical information on exposure and contamination levels. A blue print size digitizer is used for input. The computer program retains facility floor plans in three dimensional arrays. The software accesses an eight pen color plotter for output. The plotter generates color plots of the floor plans and safety systems on 8 1/2 x 11 or 20 x 30 paper or on overhead transparencies for reports and presentations

Recalling ISX shot data files from the off-line archive

International Nuclear Information System (INIS)

Stanton, J.S.

1981-02-01

This document describes a set of computer programs designed to allow access to ISX shot data files stored on off-line disk packs. The programs accept user requests for data files and build a queue of end requests. When an operator is available to mount the necessary disk packs, the system copies the requested files to an on-line disk area. The program runs on the Fusion Energy Division's DECsystem-10 computer. The request queue is implemented under the System 1022 data base management system. The support programs are coded in MACRO-10 and FORTRAN-10

Speed up of MCACE, a Monte Carlo code for evaluation of shielding safety, by parallel computer, (3)

International Nuclear Information System (INIS)

Takano, Makoto; Masukawa, Fumihiro; Naito, Yoshitaka; Onodera, Emi; Imawaka, Tsuneyuki; Yoda, Yoshihisa.

1993-07-01

The parallel computing of the MCACE code has been studied on two platforms; 1) Shared Memory Type Vector-Parallel Computer Monte-4 and 2) Networked Several Workstations. On the Monte-4, a disk-file has been allocated to collect all results computed by 4 CPUs in parallel, executing the copy of the MCACE code on each CPU. On the workstations under network environment, two parallel models have been evaluated; 1) a host-node model and 2) the model used on the Monte-4 where no software for parallelization has been employed but only standard FORTRAN language. The measurement of computing times has showed that speed up of about 3 times has been achieved by using 4 CPUs of the Monte-4. Further, connecting 4 workstations by network, the computing speed by parallelization has achieved faster than our scalar main frame computer, FACOM M-780. (author)

Utilizing HDF4 File Content Maps for the Cloud

Science.gov (United States)

Lee, Hyokyung Joe

2016-01-01

We demonstrate a prototype study that HDF4 file content map can be used for efficiently organizing data in cloud object storage system to facilitate cloud computing. This approach can be extended to any binary data formats and to any existing big data analytics solution powered by cloud computing because HDF4 file content map project started as long term preservation of NASA data that doesn't require HDF4 APIs to access data.

New technique for determining unavailability of computer controlled safety systems

International Nuclear Information System (INIS)

Fryer, M.O.; Bruske, S.Z.

1984-04-01

The availability of a safety system for a fusion reactor is determined. A fusion reactor processes tritium and requires an Emergency Tritium Cleanup (ETC) system for accidental tritium releases. The ETC is computer controlled and because of its complexity, is an excellent candidate for this analysis. The ETC system unavailability, for preliminary untested software, is calculated based on different assumptions about operator response. These assumptions are: (a) the operator shuts down the system after the first indication of plant failure; (b) the operator shuts down the system after following optimized failure verification procedures; or (c) the operator is taken out of the decision process, and the computer uses the optimized failure verification procedures

29 CFR 4000.28 - What if I send a computer disk?

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false What if I send a computer disk? 4000.28 Section 4000.28... I send a computer disk? (a) In general. We determine your filing or issuance date for a computer... paragraph (b) of this section. (1) Filings. For computer-disk filings, we may treat your submission as...

Concepts and techniques: Active electronics and computers in safety-critical accelerator operation

International Nuclear Information System (INIS)

Frankel, R.S.

1995-01-01

The Relativistic Heavy Ion Collider (RHIC) under construction at Brookhaven National Laboratory, requires an extensive Access Control System to protect personnel from Radiation, Oxygen Deficiency and Electrical hazards. In addition, the complicated nature of operation of the Collider as part of a complex of other Accelerators necessitates the use of active electronic measurement circuitry to ensure compliance with established Operational Safety Limits. Solutions were devised which permit the use of modern computer and interconnections technology for Safety-Critical applications, while preserving and enhancing, tried and proven protection methods. In addition a set of Guidelines, regarding required performance for Accelerator Safety Systems and a Handbook of design criteria and rules were developed to assist future system designers and to provide a framework for internal review and regulation

Concepts and techniques: Active electronics and computers in safety-critical accelerator operation

Energy Technology Data Exchange (ETDEWEB)

Frankel, R.S.

1995-12-31

The Relativistic Heavy Ion Collider (RHIC) under construction at Brookhaven National Laboratory, requires an extensive Access Control System to protect personnel from Radiation, Oxygen Deficiency and Electrical hazards. In addition, the complicated nature of operation of the Collider as part of a complex of other Accelerators necessitates the use of active electronic measurement circuitry to ensure compliance with established Operational Safety Limits. Solutions were devised which permit the use of modern computer and interconnections technology for Safety-Critical applications, while preserving and enhancing, tried and proven protection methods. In addition a set of Guidelines, regarding required performance for Accelerator Safety Systems and a Handbook of design criteria and rules were developed to assist future system designers and to provide a framework for internal review and regulation.

Environmental tests of a digital safety channel: An investigation of stress-related vulnerabilities of computer-based safety system

International Nuclear Information System (INIS)

Korsah, K.; Wilson, T.L.; Wood, R.; Tanaka, T.

1997-01-01

This article presents the results of environmental stress tests performed on an experimental digital safety channel (EDSC) assembled at the Oak Ridge National Laboratory as part of the Qualification of Advanced Instrumentation and Controls Systems Research program, which was sponsored by the US Nuclear Regulatory Commission. The program is expected to provide recommendations for environmental qualification of digital safety systems. The purpose of the study was to investigate potential vulnerabilities of distributed computer systems used in safety applications when subjected to environmental stressors. The EDSC assembled for the tests employs technologies and digital subsystems representative of those proposed for use in advanced light-water reactors or as retrofits in existing plants. Subsystems include computers, electrical and optical serial communication links, fiber-optic network links, analog-to-digital and digital-to-analog converters, and multiplexers. The EDSC was subjected to selected stressors that are a potential risk to digital equipment in a mild environment. The selected stressors were electromagnetic and radiofrequency interferences (EMI-RFI), temperature, humidity, and smoke exposure. The stressors were applied at levels of intensity considerably higher than the safety channel is likely to experience in a normal nuclear power plant environment. Ranges of stress were selected at a sufficiently high level to induce errors so that failure modes that are characteristic of the technologies employed could be identified. On the basis of the incidence of functional errors observed during testing, EMI-RFI, smoke exposure, and high temperature coupled with high relative humidity, in that order, were found to have the greatest impact of the stressors investigated. The most prevalent stressor-induced upsets, as well as the most severe, were found to occur during the EMI-RFI tests

Cloud object store for checkpoints of high performance computing applications using decoupling middleware

Science.gov (United States)

Bent, John M.; Faibish, Sorin; Grider, Gary

2016-04-19

Cloud object storage is enabled for checkpoints of high performance computing applications using a middleware process. A plurality of files, such as checkpoint files, generated by a plurality of processes in a parallel computing system are stored by obtaining said plurality of files from said parallel computing system; converting said plurality of files to objects using a log structured file system middleware process; and providing said objects for storage in a cloud object storage system. The plurality of processes may run, for example, on a plurality of compute nodes. The log structured file system middleware process may be embodied, for example, as a Parallel Log-Structured File System (PLFS). The log structured file system middleware process optionally executes on a burst buffer node.

Advice of the French institute of radiation protection and nuclear safety about the 'Clay 2005' file

International Nuclear Information System (INIS)

2005-01-01

The French institute of radiation protection and nuclear safety (IRSN) presents in this document its evaluation of the 'Clay 2005' file made by the ANDRA and which aims at demonstrating the feasibility of a disposal facility for high level and long living rad-wastes in the argillite formation of the Bure site. The critical points of the safety have been considered more thoroughly, together with the uncertainties concerning some important data and phenomena in relation with the confining properties of such a disposal facility. The basic geologic data gathered by the ANDRA about the Callovo-Oxfordian clay formation of the Bure site are sufficient to confirm the favorable intrinsic properties of this formation with respect to the confinement of wastes. The main possible disturbances of internal and external origin (thermal, hydrological, mechanical, chemical, climatic change, earthquakes, erosion..) would have no redhibitory impact on the overall confining capacity of the facility. The design safety principles retained for the exploitation of the facility and the post-closure safety aspects are globally satisfactory. Therefore, the IRSN considers the disposal of rad-wastes in the Callovo-Oxfordian argilite formation as feasible but in the case of a continuation of this project, several complementary informations would have to be supplied in particular concerning: the possible fracturing of the host and surrounding formations, the possibility of localized inhomogeneous fluid flows inside the surrounding formations, the improvement of our knowledge about the changes of the mechanical, physical and chemical properties of the site rocks and of concretes with time, the dimensioning of the metallic components of the facility (shafts, containers..), and the efficiency of the ventilation system with respect to the explosion risks inside B-type waste alveoles. (J.S.)

Computer and computer graphics support for the ALARA program

International Nuclear Information System (INIS)

Paine, D.; Hall, C.J.

1984-01-01

Computer programs have been developed which support three aspects of the ALARA program at Rockwell Hanford Operations (RHO): 1) Setting annual dose and skin contamination goals, 2) Analyzing trends in operational organizations' dose, numbers of skin contaminations, or radiation occurrences, and 3) Presenting graphic displays to enhance worker safety awareness. Programs have been written which search dosemetry files and produce histograms of annual occupational exposure and skin contamination histories utilizing the DISSPLA software or a desk top color graphics terminal. These programs and associated graphics are used to assemble dose and skin contamination information in a summary format so that ALARA teams can assess the past year's performance and establish reduction goals for the coming year. In addition, the graphics provide a management tool for recognizing desirable or undesirable trends in an organization's occupational dose or number of skin contaminations. Desk top graphics capabilities have been used to display safety-related data to enhance management review and worker awareness of radiological and industrial safety conditions in the work area. The following graphs are prepared on a monthly basis: 1) Numbers of skin contaminations company wide and for specific operating organizations within the company, 2) Numbers of radiation occurrences, 3) Dose histories for specific operational organizations, 4) Numbers of OSHA recordable incidents, 5) OSHA recordable incident rates and severity levels and 6) Lost workday cases

File access prediction using neural networks.

Science.gov (United States)

Patra, Prashanta Kumar; Sahu, Muktikanta; Mohapatra, Subasish; Samantray, Ronak Kumar

2010-06-01

One of the most vexing issues in design of a high-speed computer is the wide gap of access times between the memory and the disk. To solve this problem, static file access predictors have been used. In this paper, we propose dynamic file access predictors using neural networks to significantly improve upon the accuracy, success-per-reference, and effective-success-rate-per-reference by using neural-network-based file access predictor with proper tuning. In particular, we verified that the incorrect prediction has been reduced from 53.11% to 43.63% for the proposed neural network prediction method with a standard configuration than the recent popularity (RP) method. With manual tuning for each trace, we are able to improve upon the misprediction rate and effective-success-rate-per-reference using a standard configuration. Simulations on distributed file system (DFS) traces reveal that exact fit radial basis function (RBF) gives better prediction in high end system whereas multilayer perceptron (MLP) trained with Levenberg-Marquardt (LM) backpropagation outperforms in system having good computational capability. Probabilistic and competitive predictors are the most suitable for work stations having limited resources to deal with and the former predictor is more efficient than the latter for servers having maximum system calls. Finally, we conclude that MLP with LM backpropagation algorithm has better success rate of file prediction than those of simple perceptron, last successor, stable successor, and best k out of m predictors.

Requirement and prospect of nuclear data activities for nuclear safety

International Nuclear Information System (INIS)

Kimura, Itsuro

2000-01-01

Owing to continuous efforts by the members of JNDC (Japanese Nuclear Data Committee) and Nuclear Data Center in JAERI (Japan Atomic Energy Research Institute), several superb evaluated nuclear data files, such as JENDL, FP (fission product) yields and decay heat, have been compiled in Japan and opened to the world. However, they are seldom adopted in safety design and safety evaluation of light water reactors and are hardly found in related safety regulatory guidelines and standards except the decay heat. In this report, shown are a few examples of presently used nuclear data in the safety design and the safety evaluation of PWRs (pressurized water reactors) and so forth. And then, several procedures are recommended in order to enhance more utilization of Japanese evaluated nuclear data files for nuclear safety. (author)

pcircle - A Suite of Scalable Parallel File System Tools

Energy Technology Data Exchange (ETDEWEB)

2015-10-01

Most of the software related to file system are written for conventional local file system, they are serialized and can't take advantage of the benefit of a large scale parallel file system. "pcircle" software builds on top of ubiquitous MPI in cluster computing environment and "work-stealing" pattern to provide a scalable, high-performance suite of file system tools. In particular - it implemented parallel data copy and parallel data checksumming, with advanced features such as async progress report, checkpoint and restart, as well as integrity checking.

Processing techniques for data from the Kuosheng Unit 1 shakedown safety-relief-valve tests

International Nuclear Information System (INIS)

McCauley, E.W.; Rompel, S.L.; Weaver, H.J.; Altenbach, T.J.

1982-08-01

This report describes techniques developed at the Lawrence Livermore National Laobratory, Livermore, CA for processing original data from the Taiwan Power Company's Kuosheng MKIII Unit 1 Safety Relief Valve Shakedown Tests conducted in April/May 1981. The computer codes used, TPSORT, TPPLOT, and TPPSD, form a special evaluation system for treating the data from its original packed binary form to ordered, calibrated ASCII transducer files and then to production of time-history plots, numerical output files, and spectral analyses. Using the data processing techniques described, a convenient means of independently examining and analyzing a unique data base for steam condensation phenomena in the MARKIII wetwell is described. The techniques developed for handling these data are applicable to the treatment of similar, but perhaps differently structured, experiment data sets

Micro computed tomography evaluation of the Self-adjusting file and ProTaper Universal system on curved mandibular molars.

Science.gov (United States)

Serefoglu, Burcu; Piskin, Beyser

2017-09-26

The aim of this investigation was to compare the cleaning and shaping efficiency of Self-adjusting file and Protaper, and to assess the correlation between root canal curvature and working time in mandibular molars using micro-computed tomography. Twenty extracted mandibular molars instrumented with Protaper and Self-adjusting file and the total working time was measured in mesial canals. The changes in canal volume, surface area and structure model index, transportation, uninstrumented area and the correlation between working-time and the curvature were analyzed. Although no statistically significant difference was observed between two systems in distal canals (p>0.05), a significantly higher amount of removed dentin volume and lower uninstrumented area were provided by Protaper in mesial canals (p<0.0001). A correlation between working-time and the canal-curvature was also observed in mesial canals for both groups (SAFr 2 =0.792, p<0.0004, PTUr 2 =0.9098, p<0.0001).

NASIS data base management system: IBM 360 TSS implementation. Volume 6: NASIS message file

Science.gov (United States)

1973-01-01

The message file for the NASA Aerospace Safety Information System (NASIS) is discussed. The message file contains all the message and term explanations for the system. The data contained in the file can be broken down into three separate sections: (1) global terms, (2) local terms, and (3) system messages. The various terms are defined and their use within the system is explained.

Globus File Transfer Services | High-Performance Computing | NREL

Science.gov (United States)

installed on the systems at both ends of the data transfer. The NREL endpoint is nrel#globus. Click Login on the Globus web site. On the login page select "Globus ID" as the login method and click Login to the Globus website. From the Manage Data drop down menu, select Transfer Files. Then click Get

Validation of computer codes used in the safety analysis of Canadian research reactors

International Nuclear Information System (INIS)

Bishop, W.E.; Lee, A.G.

1998-01-01

AECL has embarked on a validation program for the suite of computer codes that it uses in performing the safety analyses for its research reactors. Current focus is on codes used for the analysis of the two MAPLE reactors under construction at Chalk River but the program will be extended to include additional codes that will be used for the Irradiation Research Facility. The program structure is similar to that used for the validation of codes used in the safety analyses for CANDU power reactors. (author)

Reliability analysis and computation of computer-based safety instrumentation and control used in German nuclear power plant. Final report

International Nuclear Information System (INIS)

Ding, Yongjian; Krause, Ulrich; Gu, Chunlei

2014-01-01

The trend of technological advancement in the field of safety instrumentation and control (I and C) leads to increasingly frequent use of computer-based (digital) control systems which consisting of distributed, connected bus communications computers and their functionalities are freely programmable by qualified software. The advantages of the new I and C system over the old I and C system with hard-wired technology are e.g. in the higher flexibility, cost-effective procurement of spare parts, higher hardware reliability (through higher integration density, intelligent self-monitoring mechanisms, etc.). On the other hand, skeptics see the new technology with the computer-based I and C a higher potential by influences of common cause failures (CCF), and the easier manipulation by sabotage (IT Security). In this joint research project funded by the Federal Ministry for Economical Affaires and Energy (BMWi) (2011-2014, FJZ 1501405) the Otto-von-Guericke-University Magdeburg and Magdeburg-Stendal University of Applied Sciences are therefore trying to develop suitable methods for the demonstration of the reliability of the new instrumentation and control systems with the focus on the investigation of CCF. This expertise of both houses shall be extended to this area and a scientific contribution to the sound reliability judgments of the digital safety I and C in domestic and foreign nuclear power plants. First, the state of science and technology will be worked out through the study of national and international standards in the field of functional safety of electrical and I and C systems and accompanying literature. On the basis of the existing nuclear Standards the deterministic requirements on the structure of the new digital I and C system will be determined. The possible methods of reliability modeling will be analyzed and compared. A suitable method called multi class binomial failure rate (MCFBR) which was successfully used in safety valve applications will be

An evaluation of The Great Escape: can an interactive computer game improve young children's fire safety knowledge and behaviors?

Science.gov (United States)

Morrongiello, Barbara A; Schwebel, David C; Bell, Melissa; Stewart, Julia; Davis, Aaron L

2012-07-01

Fire is a leading cause of unintentional injury and, although young children are at particularly increased risk, there are very few evidence-based resources available to teach them fire safety knowledge and behaviors. Using a pre-post randomized design, the current study evaluated the effectiveness of a computer game (The Great Escape) for teaching fire safety information to young children (3.5-6 years). Using behavioral enactment procedures, children's knowledge and behaviors related to fire safety were compared to a control group of children before and after receiving the intervention. The results indicated significant improvements in knowledge and fire safety behaviors in the intervention group but not the control. Using computer games can be an effective way to promote young children's understanding of safety and how to react in different hazardous situations.

75 FR 30839 - Privacy Act of 1974; CMS Computer Match No. 2010-03, HHS Computer Match No. 1003, SSA Computer...

Science.gov (United States)

2010-06-02

... 1974; CMS Computer Match No. 2010-03, HHS Computer Match No. 1003, SSA Computer Match No. 1048, IRS... Services (CMS). ACTION: Notice of renewal of an existing computer matching program (CMP) that has an...'' section below for comment period. DATES: Effective Dates: CMS filed a report of the Computer Matching...

Cloud object store for archive storage of high performance computing data using decoupling middleware

Science.gov (United States)

Bent, John M.; Faibish, Sorin; Grider, Gary

2015-06-30

Cloud object storage is enabled for archived data, such as checkpoints and results, of high performance computing applications using a middleware process. A plurality of archived files, such as checkpoint files and results, generated by a plurality of processes in a parallel computing system are stored by obtaining the plurality of archived files from the parallel computing system; converting the plurality of archived files to objects using a log structured file system middleware process; and providing the objects for storage in a cloud object storage system. The plurality of processes may run, for example, on a plurality of compute nodes. The log structured file system middleware process may be embodied, for example, as a Parallel Log-Structured File System (PLFS). The log structured file system middleware process optionally executes on a burst buffer node.

A data compression algorithm for nuclear spectrum files

International Nuclear Information System (INIS)

Mika, J.F.; Martin, L.J.; Johnston, P.N.

1990-01-01

The total space occupied by computer files of spectra generated in nuclear spectroscopy systems can lead to problems of storage, and transmission time. An algorithm is presented which significantly reduces the space required to store nuclear spectra, without loss of any information content. Testing indicates that spectrum files can be routinely compressed by a factor of 5. (orig.)

Probabilistic safety assessment in the chemical and nuclear industries

CERN Document Server

Fullwood, Ralph R

2000-01-01

Probabilistic Safety Analysis (PSA) determines the probability and consequences of accidents, hence, the risk. This subject concerns policy makers, regulators, designers, educators and engineers working to achieve maximum safety with operational efficiency. Risk is analyzed using methods for achieving reliability in the space program. The first major application was to the nuclear power industry, followed by applications to the chemical industry. It has also been applied to space, aviation, defense, ground, and water transportation. This book is unique in its treatment of chemical and nuclear risk. Problems are included at the end of many chapters, and answers are in the back of the book. Computer files are provided (via the internet), containing reliability data, a calculator that determines failure rate and uncertainty based on field experience, pipe break calculator, event tree calculator, FTAP and associated programs for fault tree analysis, and a units conversion code. It contains 540 references and many...

The crystallographic information file (CIF): A new standard archive file for crystallography

International Nuclear Information System (INIS)

Hall, S.R.; Allen, F.H.; Brown, I.D.

1991-01-01

The specification of a new standard Crystallographic Information File (CIF) is described. Its development is based on the Self-Defining Text Archieve and Retrieval (STAR) procedure. The CIF is a general, flexible and easily extensible free-format archive file; it is human and machine readable and can be edited by a simple editor. The CIF is designed for the electronic transmission of crystallographic data between individual laboratories, journals and databases: It has been adopted by the International Union of Crystallography as the recommended medium for this purpose. The file consists of data names and data items, together with a loop facility for repeated items. The data names, constructed hierarchically so as to form data categories, are self-descriptive within a 32-character limit. The sorted list of data names, together with their precise definitions, constitutes the CIF dictionary (core version 1991). The CIF core dictionary is presented in full and covers the fundamental and most commonly used data items relevant to crystal structure analysis. The dictionary is also available as an electronic file suitable for CIF computer applications. Future extensions to the dictionary will include data items used in more specialized areas of crystallography. (orig.)

Is Model-Based Development a Favorable Approach for Complex and Safety-Critical Computer Systems on Commercial Aircraft?

Science.gov (United States)

Torres-Pomales, Wilfredo

2014-01-01

A system is safety-critical if its failure can endanger human life or cause significant damage to property or the environment. State-of-the-art computer systems on commercial aircraft are highly complex, software-intensive, functionally integrated, and network-centric systems of systems. Ensuring that such systems are safe and comply with existing safety regulations is costly and time-consuming as the level of rigor in the development process, especially the validation and verification activities, is determined by considerations of system complexity and safety criticality. A significant degree of care and deep insight into the operational principles of these systems is required to ensure adequate coverage of all design implications relevant to system safety. Model-based development methodologies, methods, tools, and techniques facilitate collaboration and enable the use of common design artifacts among groups dealing with different aspects of the development of a system. This paper examines the application of model-based development to complex and safety-critical aircraft computer systems. Benefits and detriments are identified and an overall assessment of the approach is given.

An information retrieval system for research file data

Science.gov (United States)

Joan E. Lengel; John W. Koning

1978-01-01

Research file data have been successfully retrieved at the Forest Products Laboratory through a high-speed cross-referencing system involving the computer program FAMULUS as modified by the Madison Academic Computing Center at the University of Wisconsin. The method of data input, transfer to computer storage, system utilization, and effectiveness are discussed....

Computer-based training at Sellafield

International Nuclear Information System (INIS)

Cartmell, A.; Evans, M.C.

1986-01-01

British Nuclear Fuel Limited (BNFL) operate the United Kingdom's spent-fuel receipt, storage, and reprocessing complex at Sellafield. Spent fuel from graphite-moderated CO 2 -cooled Magnox reactors has been reprocessed at Sellafield for 22 yr. Spent fuel from light water and advanced gas reactors is stored pending reprocessing in the Thermal Oxide Reprocessing Plant currently being constructed. The range of knowledge and skills needed for plant operation, construction, and commissioning represents a formidable training requirement. In addition, employees need to be acquainted with company practices and procedures. Computer-based training (CBT) is expected to play a significant role in this process. In this paper, current applications of CBT to the filed of nuclear criticality safety are described and plans for the immediate future are outlined

The global unified parallel file system (GUPFS) project: FY 2002 activities and results

Energy Technology Data Exchange (ETDEWEB)

Butler, Gregory F.; Lee, Rei Chi; Welcome, Michael L.

2003-04-07

The Global Unified Parallel File System (GUPFS) project is a multiple-phase, five-year project at the National Energy Research Scientific Computing (NERSC) Center to provide a scalable, high performance, high bandwidth, shared file system for all the NERSC production computing and support systems. The primary purpose of the GUPFS project is to make it easier to conduct advanced scientific research using the NERSC systems. This is to be accomplished through the use of a shared file system providing a unified file namespace, operating on consolidated shared storage that is directly accessed by all the NERSC production computing and support systems. During its first year, FY 2002, the GUPFS project focused on identifying, testing, and evaluating existing and emerging shared/cluster file system, SAN fabric, and storage technologies; identifying NERSC user input/output (I/O) requirements, methods, and mechanisms; and developing appropriate benchmarking methodologies and benchmark codes for a parallel environment. This report presents the activities and progress of the GUPFS project during its first year, the results of the evaluations conducted, and plans for near-term and longer-term investigations.

78 FR 47014 - Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear...

Science.gov (United States)

2013-08-02

.... ML12354A524. 3. Revision 1 of RG 1.170, ``Test Documentation for Digital Computer Software used in Safety... is in ADAMS at Accession No. ML12354A531. 4. Revision 1 of RG 1.171, ``Software Unit Testing for... Software Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION...

LASIP-III, a generalized processor for standard interface files

International Nuclear Information System (INIS)

Bosler, G.E.; O'Dell, R.D.; Resnik, W.M.

1976-03-01

The LASIP-III code was developed for processing Version III standard interface data files which have been specified by the Committee on Computer Code Coordination. This processor performs two distinct tasks, namely, transforming free-field format, BCD data into well-defined binary files and providing for printing and punching data in the binary files. While LASIP-III is exported as a complete free-standing code package, techniques are described for easily separating the processor into two modules, viz., one for creating the binary files and one for printing the files. The two modules can be separated into free-standing codes or they can be incorporated into other codes. Also, the LASIP-III code can be easily expanded for processing additional files, and procedures are described for such an expansion. 2 figures, 8 tables

CryptoCache: A Secure Sharable File Cache for Roaming Users

DEFF Research Database (Denmark)

Jensen, Christian D.

2000-01-01

. Conventional distributed file systems cache everything locally or not at all; there is no possibility to cache files on nearby nodes.In this paper we present the design of a secure cache system called CryptoCache that allows roaming users to cache files on untrusted file hosting servers. The system allows...... flexible sharing of cached files among unauthenticated users, i.e. unlike most distributed file systems CryptoCache does not require a global authentication framework.Files are encrypted when they are transferred over the network and while stored on untrusted servers. The system uses public key......Small mobile computers are now sufficiently powerful to run many applications, but storage capacity remains limited so working files cannot be cached or stored locally. Even if files can be stored locally, the mobile device is not powerful enough to act as server in collaborations with other users...

GEODOC: the GRID document file, record structure and data element description

Energy Technology Data Exchange (ETDEWEB)

Trippe, T.; White, V.; Henderson, F.; Phillips, S.

1975-11-06

The purpose of this report is to describe the information structure of the GEODOC file. GEODOC is a computer based file which contains the descriptive cataloging and indexing information for all documents processed by the National Geothermal Information Resource Group. This file (along with other GRID files) is managed by DBMS, the Berkeley Data Base Management System. Input for the system is prepared using the IRATE Text Editing System with its extended (12 bit) character set, or punched cards.

NASIS data base management system - IBM 360/370 OS MVT implementation. 6: NASIS message file

Science.gov (United States)

1973-01-01

The message file for the NASA Aerospace Safety Information System (NASIS) is discussed. The message file contains all the message and term explanations for the system. The data contained in the file can be broken down into three separate sections: (1) global terms, (2) local terms, and (3) system messages. The various terms are defined and their use within the system is explained.

Virus Alert: Ten Steps to Safe Computing.

Science.gov (United States)

Gunter, Glenda A.

1997-01-01

Discusses computer viruses and explains how to detect them; discusses virus protection and the need to update antivirus software; and offers 10 safe computing tips, including scanning floppy disks and commercial software, how to safely download files from the Internet, avoiding pirated software copies, and backing up files. (LRW)

Comparative Analysis of Canal Centering Ability of Different Single File Systems Using Cone Beam Computed Tomography- An In-Vitro Study.

Science.gov (United States)

Agarwal, Rolly S; Agarwal, Jatin; Jain, Pradeep; Chandra, Anil

2015-05-01

The ability of an endodontic instrument to remain centered in the root canal system is one of the most important characteristic influencing the clinical performance of a particular file system. Thus, it is important to assess the canal centering ability of newly introduced single file systems before they can be considered a viable replacement of full-sequence rotary file systems. The aim of the study was to compare the canal transportation, centering ability, and time taken for preparation of curved root canals after instrumentation with single file systems One Shape and Wave One, using cone-beam computed tomography (CBCT). Sixty mesiobuccal canals of mandibular molars with an angle of curvature ranging from 20(o) to 35(o) were divided into three groups of 20 samples each: ProTaper PT (group I) - full-sequence rotary control group, OneShape OS (group II)- single file continuous rotation, WaveOne WO - single file reciprocal motion (group III). Pre instrumentation and post instrumentation three-dimensional CBCT images were obtained from root cross-sections at 3mm, 6mm and 9mm from the apex. Scanned images were then accessed to determine canal transportation and centering ability. The data collected were evaluated using one-way analysis of variance (ANOVA) with Tukey's honestly significant difference test. It was observed that there were no differences in the magnitude of transportation between the rotary instruments (p >0.05) at both 3mm as well as 6mm from the apex. At 9 mm from the apex, Group I PT showed significantly higher mean canal transportation and lower centering ability (0.19±0.08 and 0.39±0.16), as compared to Group II OS (0.12±0.07 and 0.54±0.24) and Group III WO (0.13±0.06 and 0.55±0.18) while the differences between OS and WO were not statistically significant. It was concluded that there was minor difference between the tested groups. Single file systems demonstrated average canal transportation and centering ability comparable to full sequence

Comparative Analysis of Canal Centering Ability of Different Single File Systems Using Cone Beam Computed Tomography- An In-Vitro Study

Science.gov (United States)

Agarwal, Jatin; Jain, Pradeep; Chandra, Anil

2015-01-01

Background The ability of an endodontic instrument to remain centered in the root canal system is one of the most important characteristic influencing the clinical performance of a particular file system. Thus, it is important to assess the canal centering ability of newly introduced single file systems before they can be considered a viable replacement of full-sequence rotary file systems. Aim The aim of the study was to compare the canal transportation, centering ability, and time taken for preparation of curved root canals after instrumentation with single file systems One Shape and Wave One, using cone-beam computed tomography (CBCT). Materials and Methods Sixty mesiobuccal canals of mandibular molars with an angle of curvature ranging from 20o to 35o were divided into three groups of 20 samples each: ProTaper PT (group I) – full-sequence rotary control group, OneShape OS (group II)- single file continuous rotation, WaveOne WO – single file reciprocal motion (group III). Pre instrumentation and post instrumentation three-dimensional CBCT images were obtained from root cross-sections at 3mm, 6mm and 9mm from the apex. Scanned images were then accessed to determine canal transportation and centering ability. The data collected were evaluated using one-way analysis of variance (ANOVA) with Tukey’s honestly significant difference test. Results It was observed that there were no differences in the magnitude of transportation between the rotary instruments (p >0.05) at both 3mm as well as 6mm from the apex. At 9 mm from the apex, Group I PT showed significantly higher mean canal transportation and lower centering ability (0.19±0.08 and 0.39±0.16), as compared to Group II OS (0.12±0.07 and 0.54±0.24) and Group III WO (0.13±0.06 and 0.55±0.18) while the differences between OS and WO were not statistically significant Conclusion It was concluded that there was minor difference between the tested groups. Single file systems demonstrated average canal

Manual on quality assurance for computer software related to the safety of nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

The objective of the Manual is to provide guidance in the assurance of quality of specification, design, maintenance and use of computer software related to items and activities important to safety (hereinafter referred to as safety related) in nuclear power plants. This guidance is consistent with, and supplements, the requirements and recommendations of Quality Assurance for Safety in Nuclear Power Plants: A Code of Practice, 50-C-QA, and related Safety Guides on quality assurance for nuclear power plants. Annex A identifies the IAEA documents referenced in the Manual. The Manual is intended to be of use to all those who, in any way, are involved with software for safety related applications for nuclear power plants, including auditors who may be called upon to audit management systems and product software. Figs

ChemEngine: harvesting 3D chemical structures of supplementary data from PDF files.

Science.gov (United States)

Karthikeyan, Muthukumarasamy; Vyas, Renu

2016-01-01

Digital access to chemical journals resulted in a vast array of molecular information that is now available in the supplementary material files in PDF format. However, extracting this molecular information, generally from a PDF document format is a daunting task. Here we present an approach to harvest 3D molecular data from the supporting information of scientific research articles that are normally available from publisher's resources. In order to demonstrate the feasibility of extracting truly computable molecules from PDF file formats in a fast and efficient manner, we have developed a Java based application, namely ChemEngine. This program recognizes textual patterns from the supplementary data and generates standard molecular structure data (bond matrix, atomic coordinates) that can be subjected to a multitude of computational processes automatically. The methodology has been demonstrated via several case studies on different formats of coordinates data stored in supplementary information files, wherein ChemEngine selectively harvested the atomic coordinates and interpreted them as molecules with high accuracy. The reusability of extracted molecular coordinate data was demonstrated by computing Single Point Energies that were in close agreement with the original computed data provided with the articles. It is envisaged that the methodology will enable large scale conversion of molecular information from supplementary files available in the PDF format into a collection of ready- to- compute molecular data to create an automated workflow for advanced computational processes. Software along with source codes and instructions available at https://sourceforge.net/projects/chemengine/files/?source=navbar.Graphical abstract.

Evaluation of Single File Systems Reciproc, Oneshape, and WaveOne using Cone Beam Computed Tomography –An In Vitro Study

Science.gov (United States)

Dhingra, Annil; Miglani, Anjali

2015-01-01

Background Successful endodontic therapy depends on many factor, one of the most important step in any root canal treatment is root canal preparation. In addition, respecting the original shape of the canal is of the same importance; otherwise, canal aberrations such as transportation will be created. Aim The purpose of this study is to compare and evaluate Reciprocating WaveOne ,Reciproc and Rotary Oneshape Single File Instrumentation System On Cervical Dentin Thickness, Cross Sectional Area and Canal Transportation on First Mandibular Molar Using Cone Beam Computed Tomography. Materials and Methods Sixty Mandibular First Molars extracted due to periodontal reason was collected from the Department of Oral and Maxillofacial. Teeth were prepared using one rotary and two reciprocating single file system. Teeth were divided into 3 groups 20 teeth in each group. Pre instrumentation and Post instrumentation scans was done and evaluated for three parameters Canal Transportation, Cervical Dentinal Thickness, Cross-sectional Area. Results were analysed statistically using ANOVA, Post-Hoc Tukey analysis. Results The change in cross-sectional area after filing showed significant difference at 0mm, 1mm, 2mm and 7mm (pfile system over a distance of 7 mm (starting from 0mm and then evaluation at 1mm, 2mm, 3mm, 5mm and 7mm), the results showed a significant difference among the file systems at various lengths (p= 0.014, 0.046, 0.004, 0.028, 0.005 & 0.029 respectively). Mean value of cervical dentinal removal is maximum at all the levels for oneshape and minimum for waveone showing the better quality of waveone and reciproc over oneshape file system. Significant difference was found at 9mm, 11mm and 12mm between all the three file systems (p<0.001,< 0.001, <0.001). Conclusion It was concluded that reciprocating motion is better than rotary motion in all the three parameters Canal Transportation, Cross-sectional Area, Cervical Dentinal Thickness. PMID:26023639

RRB / SSI Interface Checkwriting Integrated Computer Operation Extract File (CHICO)

Data.gov (United States)

Social Security Administration — This monthly file provides SSA with information about benefit payments made to railroad retirement beneficiaries. SSA uses this data to verify Supplemental Security...

Fundamental challenging problems for developing new nuclear safety standard computer codes

International Nuclear Information System (INIS)

Wong, P.K.; Wong, A.E.; Wong, A.

2005-01-01

Based on the claims of the US Basic patents number 5,084,232; 5,848,377 and 6,430,516 that can be obtained from typing the Patent Numbers into the Box of the Web site http://164.195.100.11/netahtml/srchnum.htm and their associated published technical papers having been presented and published at International Conferences in the last three years and that all these had been sent into US-NRC by E-mail on March 26, 2003 at 2:46 PM., three fundamental challenging problems for developing new nuclear safety standard computer codes had been presented at the US-NRC RIC2003 Session W4. 2:15-3:15 PM. at the Washington D.C. Capital Hilton Hotel, Presidential Ballroom on April 16, 2003 in front of more than 800 nuclear professionals from many countries worldwide. The objective and scope of this paper is to invite all nuclear professionals to examine and evaluate all the current computer codes being used in their own countries by means of comparison of numerical data from these three specific openly challenging fundamental problems in order to set up a global safety standard for all nuclear power plants in the world. (authors)

The Improvement and Performance of Mobile Environment Using Both Cloud and Text Computing

OpenAIRE

S.Saravana Kumar; J.Lakshmi Priya; P.Hannah Jennifer; N.Jeff Monica; Fathima

2013-01-01

In this research paper presents an design model for file sharing system for ubiquitos mobile devices using both cloud and text computing. File s haring is one of the rationales for computer networks with increasing demand for file sharing ap plications and technologies in small and large enterprise networks and on the Internet. File transfer is an important process in any form of computing as we need to really share the data ac ross. ...

Dynamic file-access characteristics of a production parallel scientific workload

Science.gov (United States)

Kotz, David; Nieuwejaar, Nils

1994-01-01

Multiprocessors have permitted astounding increases in computational performance, but many cannot meet the intense I/O requirements of some scientific applications. An important component of any solution to this I/O bottleneck is a parallel file system that can provide high-bandwidth access to tremendous amounts of data in parallel to hundreds or thousands of processors. Most successful systems are based on a solid understanding of the expected workload, but thus far there have been no comprehensive workload characterizations of multiprocessor file systems. This paper presents the results of a three week tracing study in which all file-related activity on a massively parallel computer was recorded. Our instrumentation differs from previous efforts in that it collects information about every I/O request and about the mix of jobs running in a production environment. We also present the results of a trace-driven caching simulation and recommendations for designers of multiprocessor file systems.

20 CFR 726.316 - Filing and service.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Filing and service. 726.316 Section 726.316 Employees' Benefits EMPLOYMENT STANDARDS ADMINISTRATION, DEPARTMENT OF LABOR FEDERAL COAL MINE HEALTH AND SAFETY ACT OF 1969, AS AMENDED BLACK LUNG BENEFITS; REQUIREMENTS FOR COAL MINE OPERATOR'S INSURANCE Civil...

Tabulation of Fundamental Assembly Heat and Radiation Source Files

International Nuclear Information System (INIS)

T. deBues; J.C. Ryman

2006-01-01

The purpose of this calculation is to tabulate a set of computer files for use as input to the WPLOAD thermal loading software. These files contain details regarding heat and radiation from pressurized water reactor (PWR) assemblies and boiling water reactor (BWR) assemblies. The scope of this calculation is limited to rearranging and reducing the existing file information into a more streamlined set of tables for use as input to WPLOAD. The electronic source term files used as input to this calculation were generated from the output files of the SAS2H/ORIGIN-S sequence of the SCALE Version 4.3 modular code system, as documented in References 2.1.1 and 2.1.2, and are included in Attachment II

Construction of the radiation oncology teaching files system for charged particle radiotherapy.

Science.gov (United States)

Masami, Mukai; Yutaka, Ando; Yasuo, Okuda; Naoto, Takahashi; Yoshihisa, Yoda; Hiroshi, Tsuji; Tadashi, Kamada

2013-01-01

Our hospital started the charged particle therapy since 1996. New institutions for charged particle therapy are planned in the world. Our hospital are accepting many visitors from those newly planned medical institutions and having many opportunities to provide with the training to them. Based upon our experiences, we have developed the radiation oncology teaching files system for charged particle therapy. We adopted the PowerPoint of Microsoft as a basic framework of our teaching files system. By using our export function of the viewer any physician can create teaching files easily and effectively. Now our teaching file system has 33 cases for clinical and physics contents. We expect that we can improve the safety and accuracy of charged particle therapy by using our teaching files system substantially.

COMPUTING

CERN Multimedia

M. Kasemann

CCRC’08 challenges and CSA08 During the February campaign of the Common Computing readiness challenges (CCRC’08), the CMS computing team had achieved very good results. The link between the detector site and the Tier0 was tested by gradually increasing the number of parallel transfer streams well beyond the target. Tests covered the global robustness at the Tier0, processing a massive number of very large files and with a high writing speed to tapes.  Other tests covered the links between the different Tiers of the distributed infrastructure and the pre-staging and reprocessing capacity of the Tier1’s: response time, data transfer rate and success rate for Tape to Buffer staging of files kept exclusively on Tape were measured. In all cases, coordination with the sites was efficient and no serious problem was found. These successful preparations prepared the ground for the second phase of the CCRC’08 campaign, in May. The Computing Software and Analysis challen...

SACRD: a data base for fast reactor safety computer codes, general description

International Nuclear Information System (INIS)

Greene, N.M.; Forsberg, V.M.; Raiford, G.B.; Arwood, J.W.; Simpson, D.B.; Flanagan, G.F.

1979-01-01

SACRD is a data base of material properties and other handbook data needed in computer codes used for fast reactor safety studies. Data are available in the thermodynamics, heat transfer, fluid mechanics, structural mechanics, aerosol transport, meteorology, neutronics, and dosimetry areas. Tabular, graphical and parameterized data are provided in many cases. A general description of the SACRD system is presented in the report

Compendium of computer codes for the safety analysis of fast breeder reactors

International Nuclear Information System (INIS)

1977-10-01

The objective of the compendium is to provide the reader with a guide which briefly describes many of the computer codes used for liquid metal fast breeder reactor safety analyses, since it is for this system that most of the codes have been developed. The compendium is designed to address the following frequently asked questions from individuals in licensing and research and development activities: (1) What does the code do. (2) To what safety problems has it been applied. (3) What are the code's limitations. (4) What is being done to remove these limitations. (5) How does the code compare with experimental observations and other code predictions. (6) What reference documents are available

The design and development of GRASS file reservation system

International Nuclear Information System (INIS)

Huang Qiulan; Zhu Suijiang; Cheng Yaodong; Chen Gang

2010-01-01

GFRS (GRASS File Reservation System) is designed to improve the file access performance of GRASS (Grid-enabled Advanced Storage System) which is a Hierarchical Storage Management (HSM) system developed at Computing Center, Institute of High Energy Physics. GRASS can provide massive storage management and data migration, but the data migration policy is simply based factors such as pool water level, the intervals for migration and so on, so it is short of precise control over files. As for that, we design GFRS to implement user-based file reservation which is to reserve and keep the required files on disks for High Energy physicists. CFRS can improve file access speed for users by avoiding migrating frequently accessed files to tapes. In this paper we first give a brief introduction of GRASS system and then detailed architecture and implementation of GFRS. Experiments results from GFRS have shown good performance and a simple analysis is made based on it. (authors)

User's guide for the implementation of level one of the proposed American National Standard Specifications for an information interchange data descriptive file on control data 6000/7000 series computers

CERN Document Server

Wiley, R A

1977-01-01

User's guide for the implementation of level one of the proposed American National Standard Specifications for an information interchange data descriptive file on control data 6000/7000 series computers

New developments in file-based infrastructure for ATLAS event selection

Energy Technology Data Exchange (ETDEWEB)

Gemmeren, P van; Malon, D M [Argonne National Laboratory, Argonne, Illinois 60439 (United States); Nowak, M, E-mail: gemmeren@anl.go [Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)

2010-04-01

In ATLAS software, TAGs are event metadata records that can be stored in various technologies, including ROOT files and relational databases. TAGs are used to identify and extract events that satisfy certain selection predicates, which can be coded as SQL-style queries. TAG collection files support in-file metadata to store information describing all events in the collection. Event Selector functionality has been augmented to provide such collection-level metadata to subsequent algorithms. The ATLAS I/O framework has been extended to allow computational processing of TAG attributes to select or reject events without reading the event data. This capability enables physicists to use more detailed selection criteria than are feasible in an SQL query. For example, the TAGs contain enough information not only to check the number of electrons, but also to calculate their distance to the closest jet-a calculation that would be difficult to express in SQL. Another new development allows ATLAS to write TAGs directly into event data files. This feature can improve performance by supporting advanced event selection capabilities, including computational processing of TAG information, without the need for external TAG file or database access.

Prefetching in file systems for MIMD multiprocessors

Science.gov (United States)

Kotz, David F.; Ellis, Carla Schlatter

1990-01-01

The question of whether prefetching blocks on the file into the block cache can effectively reduce overall execution time of a parallel computation, even under favorable assumptions, is considered. Experiments have been conducted with an interleaved file system testbed on the Butterfly Plus multiprocessor. Results of these experiments suggest that (1) the hit ratio, the accepted measure in traditional caching studies, may not be an adequate measure of performance when the workload consists of parallel computations and parallel file access patterns, (2) caching with prefetching can significantly improve the hit ratio and the average time to perform an I/O (input/output) operation, and (3) an improvement in overall execution time has been observed in most cases. In spite of these gains, prefetching sometimes results in increased execution times (a negative result, given the optimistic nature of the study). The authors explore why it is not trivial to translate savings on individual I/O requests into consistently better overall performance and identify the key problems that need to be addressed in order to improve the potential of prefetching techniques in the environment.

The global unified parallel file system (GUPFS) project: FY 2003 activities and results

Energy Technology Data Exchange (ETDEWEB)

Butler, Gregory F.; Baird William P.; Lee, Rei C.; Tull, Craig E.; Welcome, Michael L.; Whitney Cary L.

2004-04-30

The Global Unified Parallel File System (GUPFS) project is a multiple-phase project at the National Energy Research Scientific Computing (NERSC) Center whose goal is to provide a scalable, high-performance, high-bandwidth, shared file system for all of the NERSC production computing and support systems. The primary purpose of the GUPFS project is to make the scientific users more productive as they conduct advanced scientific research at NERSC by simplifying the scientists' data management tasks and maximizing storage and data availability. This is to be accomplished through the use of a shared file system providing a unified file namespace, operating on consolidated shared storage that is accessible by all the NERSC production computing and support systems. In order to successfully deploy a scalable high-performance shared file system with consolidated disk storage, three major emerging technologies must be brought together: (1) shared/cluster file systems software, (2) cost-effective, high-performance storage area network (SAN) fabrics, and (3) high-performance storage devices. Although they are evolving rapidly, these emerging technologies individually are not targeted towards the needs of scientific high-performance computing (HPC). The GUPFS project is in the process of assessing these emerging technologies to determine the best combination of solutions for a center-wide shared file system, to encourage the development of these technologies in directions needed for HPC, particularly at NERSC, and to then put them into service. With the development of an evaluation methodology and benchmark suites, and with the updating of the GUPFS testbed system, the project did a substantial number of investigations and evaluations during FY 2003. The investigations and evaluations involved many vendors and products. From our evaluation of these products, we have found that most vendors and many of the products are more focused on the commercial market. Most vendors

Detection Of Alterations In Audio Files Using Spectrograph Analysis

Directory of Open Access Journals (Sweden)

Anandha Krishnan G

2015-08-01

Full Text Available The corresponding study was carried out to detect changes in audio file using spectrograph. An audio file format is a file format for storing digital audio data on a computer system. A sound spectrograph is a laboratory instrument that displays a graphical representation of the strengths of the various component frequencies of a sound as time passes. The objectives of the study were to find the changes in spectrograph of audio after altering them to compare altering changes with spectrograph of original files and to check for similarity and difference in mp3 and wav. Five different alterations were carried out on each audio file to analyze the differences between the original and the altered file. For altering the audio file MP3 or WAV by cutcopy the file was opened in Audacity. A different audio was then pasted to the audio file. This new file was analyzed to view the differences. By adjusting the necessary parameters the noise was reduced. The differences between the new file and the original file were analyzed. By adjusting the parameters from the dialog box the necessary changes were made. The edited audio file was opened in the software named spek where after analyzing a graph is obtained of that particular file which is saved for further analysis. The original audio graph received was combined with the edited audio file graph to see the alterations.

NASA work unit system file maintenance manual

Science.gov (United States)

1972-01-01

The NASA Work Unit System is a management information system for research tasks (i.e., work units) performed under NASA grants and contracts. It supplies profiles on research efforts and statistics on fund distribution. The file maintenance operator can add, delete and change records at a remote terminal or can submit punched cards to the computer room for batch update. The system is designed for file maintenance by a person with little or no knowledge of data processing techniques.

Standard interface files and procedures for reactor physics codes. Version IV

International Nuclear Information System (INIS)

O'Dell, R.D.

1977-09-01

Standards, procedures, and recommendations of the Committee on Computer Code Coordination for promoting the exchange of reactor physics codes are updated to Version IV status. Standards and procedures covering general programming, program structure, standard interface files, and file management and handling subroutines are included

Remote file inquiry (RFI) system

Science.gov (United States)

1975-01-01

System interrogates and maintains user-definable data files from remote terminals, using English-like, free-form query language easily learned by persons not proficient in computer programming. System operates in asynchronous mode, allowing any number of inquiries within limitation of available core to be active concurrently.

The computer vision in the service of safety and reliability in steam generators inspection services

International Nuclear Information System (INIS)

Pineiro Fernandez, P.; Garcia Bueno, A.; Cabrera Jordan, E.

2012-01-01

The actual computational vision has matured very quickly in the last ten years by facilitating new developments in various areas of nuclear application allowing to automate and simplify processes and tasks, instead or in collaboration with the people and equipment efficiently. The current computer vision (more appropriate than the artificial vision concept) provides great possibilities of also improving in terms of the reliability and safety of NPPS inspection systems.

Evaluation of the Self-Adjusting File system (SAF) for the instrumentation of primary molar root canals: a micro-computed tomographic study.

Science.gov (United States)

Kaya, E; Elbay, M; Yiğit, D

2017-06-01

The Self-Adjusting File (SAF) system has been recommended for use in permanent teeth since it offers more conservative and effective root-canal preparation when compared to traditional rotary systems. However, no study had evaluated the usage of SAF in primary teeth. The aim of this study was to evaluate and compare the use of SAF, K file (manual instrumentation) and Profile (traditional rotary instrumentation) systems for primary-tooth root-canal preparation in terms of instrumentation time and amounts of dentin removed using micro-computed tomography (μCT) technology. Study Design: The study was conducted with 60 human primary mandibular second molar teeth divided into 3 groups according to instrumentation technique: Group I: SAF (n=20); Group II: K file (n=20); Group III; Profile (n=20). Teeth were embedded in acrylic blocks and scanned with a μCT scanner prior to instrumentation. All distal root canals were prepared up to size 30 for K file,.04/30 for Profile and 2 mm thickness, size 25 for SAF; instrumentation time was recorded for each tooth, and a second μCT scan was performed after instrumentation was complete. Amounts of dentin removed were measured using the three-dimensional images by calculating the difference in root-canal volume before and after preparation. Data was statistically analysed using the Kolmogorov-Smirnov and Kruskal-Wallis tests. Manual instrumentation (K file) resulted in significantly more dentin removal when compared to rotary instrumentation (Profile and SAF), while the SAF system generated significantly less dentin removal than both manual instrumentation (K file) and traditional rotary instrumentation (Profile) (psystems. Within the experimental conditions of the present study, the SAF seems as a useful system for root-canal instrumentation in primary molars because it removed less dentin than other systems, which is especially important for the relatively thin-walled canals of primary teeth, and because it involves less

Nuclear plant fire incident data file

International Nuclear Information System (INIS)

Sideris, A.G.; Hockenbury, R.W.; Yeater, M.L.; Vesely, W.E.

1979-01-01

A computerized nuclear plant fire incident data file was developed by American Nuclear Insurers and was further analyzed by Rensselaer Polytechnic Institute with technical and monetary support provided by the Nuclear Regulatory Commission. Data on 214 fires that occurred at nuclear facilities have been entered in the file. A computer program has been developed to sort the fire incidents according to various parameters. The parametric sorts that are presented in this article are significant since they are the most comprehensive statistics presently available on fires that have occurred at nuclear facilities

Nuclear Criticality Safety Assessment Using the SCALE Computer Code Package. A demonstration based on an independent review of a real application

International Nuclear Information System (INIS)

Mennerdahl, Dennis

1998-06-01

The purpose of this project was to instruct a young scientist from the Lithuanian Energy Institute (LEI) on how to carry out an independent review of a safety report. In particular, emphasis, was to be put on how to use the personal computer version of the calculation system SCALE 4.3 in this process. Nuclear criticality safety together with radiation shielding from gamma and neutron sources were areas of interest. This report concentrates on nuclear criticality safety aspects while a separate report covers radiation shielding. The application was a proposed storage cask for irradiated fuel assemblies from the Ignalina RBMK reactors in Lithuania. The safety report contained various documents involving many design and safety considerations. A few other documents describing the Ignalina reactors and their operation were available. The time for the project was limited to approximately one month, starting 'clean' with a SCALE 4.3 CD-ROM, a thick safety report and a fast personal computer. The results should be of general interest to Swedish authorities, in particular related to shielding where experience in using advanced computer codes like those available in SCALE is limited. It has been known for many years that criticality safety is very complicated, and that independent reviews are absolutely necessary to reduce the risk from quite common errors in the safety assessments. Several important results were obtained during the project. Concerning use of SCALE 4.3, it was confirmed that a young scientist, without extensive previous experience in the code system, can learn to use essentially all options. During the project, it was obvious that familiarity with personal computers, operating systems (including network system) and office software (word processing, spreadsheet and Internet browser software) saved a lot of time. Some of the Monte Carlo calculations took several hours. Experience is valuable in quickly picking out input or source document errors. Understanding

ATLAS, an integrated structural analysis and design system. Volume 4: Random access file catalog

Science.gov (United States)

Gray, F. P., Jr. (Editor)

1979-01-01

A complete catalog is presented for the random access files used by the ATLAS integrated structural analysis and design system. ATLAS consists of several technical computation modules which output data matrices to corresponding random access file. A description of the matrices written on these files is contained herein.

16 CFR 1702.19 - Effect of filing petition.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Effect of filing petition. 1702.19 Section 1702.19 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION POISON PREVENTION PACKAGING ACT OF 1970.... Therefore, substances subject to special packaging standards shall be considered in violation of the law...

Activity-based computing: computational management of activities reflecting human intention

DEFF Research Database (Denmark)

Bardram, Jakob E; Jeuris, Steven; Houben, Steven

2015-01-01

paradigm that has been applied in personal information management applications as well as in ubiquitous, multidevice, and interactive surface computing. ABC has emerged as a response to the traditional application- and file-centered computing paradigm, which is oblivious to a notion of a user’s activity...

Radiology Teaching Files on the Internet

International Nuclear Information System (INIS)

Lim, Eun Chung; Kim, Eun Kyung

1996-01-01

There is increasing attention about radiology teaching files on the Internet in the field of diagnostic radiology. The purpose of this study was to aid in the creation of new radiology teaching file by analysing the present radiology teaching file sites on the Internet with many aspects and evaluating images on those sites, using Macintosh II ci compute r, 28.8kbps TelePort Fax/Modem, Netscape Navigator 2.0 software. The results were as follow : 1. Analysis of radiology teaching file sites (1) Country distribution was the highest in USA (57.5%). (2) Average number of cases was 186 cases and radiology teaching file sites with search engine were 9 sites (22.5%). (3) At the method of case arrangement, anatomic area type and diagnosis type were found at the 10 sites (25%) each, question and answer type was found at the 9 sites (22.5%). (4) Radiology teaching file sites with oro-maxillofacial disorder were 9 sites (22.5%). (5) At the image format, GIF format was found at the 14 sites (35%), and JPEG format found at the 14 sites (35%). (6) Created year was the highest in 1995 (43.7%). (7) Continuing case upload was found at the 35 sites (87.5%). 2. Evaluation of images on the radiology teaching files (1) Average file size of GIF format (71 Kbyte) was greater than that of JPEG format (24 Kbyte). (P<0.001) (2) Image quality of GIF format was better than that of JPEG format. (P<0.001)

Lessons Learned in Deploying the World s Largest Scale Lustre File System

Energy Technology Data Exchange (ETDEWEB)

Dillow, David A [ORNL; Fuller, Douglas [ORNL; Wang, Feiyi [ORNL; Oral, H Sarp [ORNL; Zhang, Zhe [ORNL; Hill, Jason J [ORNL; Shipman, Galen M [ORNL

2010-01-01

The Spider system at the Oak Ridge National Laboratory's Leadership Computing Facility (OLCF) is the world's largest scale Lustre parallel file system. Envisioned as a shared parallel file system capable of delivering both the bandwidth and capacity requirements of the OLCF's diverse computational environment, the project had a number of ambitious goals. To support the workloads of the OLCF's diverse computational platforms, the aggregate performance and storage capacity of Spider exceed that of our previously deployed systems by a factor of 6x - 240 GB/sec, and 17x - 10 Petabytes, respectively. Furthermore, Spider supports over 26,000 clients concurrently accessing the file system, which exceeds our previously deployed systems by nearly 4x. In addition to these scalability challenges, moving to a center-wide shared file system required dramatically improved resiliency and fault-tolerance mechanisms. This paper details our efforts in designing, deploying, and operating Spider. Through a phased approach of research and development, prototyping, deployment, and transition to operations, this work has resulted in a number of insights into large-scale parallel file system architectures, from both the design and the operational perspectives. We present in this paper our solutions to issues such as network congestion, performance baselining and evaluation, file system journaling overheads, and high availability in a system with tens of thousands of components. We also discuss areas of continued challenges, such as stressed metadata performance and the need for file system quality of service alongside with our efforts to address them. Finally, operational aspects of managing a system of this scale are discussed along with real-world data and observations.

Linking road accident data to other files : an integrated road accident recordkeeping system. Contribution in Proceedings of Seminar P 'Road Safety' held at the 14th PTHC Summer Annual Meeting, University of Sussex, England, from 14-17 July 1986. Volume P 284, p. 55-86.

NARCIS (Netherlands)

Harris, S.

1986-01-01

The road accident data which the police collect is of great value to road safety research and is used extensively. This data increases greatly in value if it can be linked to other files which contain more detailed information on exposure. Linking road accident data to other files results in what we

Linking road accident data to other files : an integrated road accident recordkeeping system. Contribution in Proceedings of Seminar P 'Road Safety' held at the 14th PTHC Summer Annual Meeting, University of Sussex, England, from 14-17 July 1986. Volume P 284, p. 55-86.

OpenAIRE

Harris, S.

1986-01-01

The road accident data which the police collect is of great value to road safety research and is used extensively. This data increases greatly in value if it can be linked to other files which contain more detailed information on exposure. Linking road accident data to other files results in what we call an Integrated Road Accident Recordkeeping System in -which the combined value of the linked files is greater than that of the sum of their individual values.

Configuration Management File Manager Developed for Numerical Propulsion System Simulation

Science.gov (United States)

Follen, Gregory J.

1997-01-01

One of the objectives of the High Performance Computing and Communication Project's (HPCCP) Numerical Propulsion System Simulation (NPSS) is to provide a common and consistent way to manage applications, data, and engine simulations. The NPSS Configuration Management (CM) File Manager integrated with the Common Desktop Environment (CDE) window management system provides a common look and feel for the configuration management of data, applications, and engine simulations for U.S. engine companies. In addition, CM File Manager provides tools to manage a simulation. Features include managing input files, output files, textual notes, and any other material normally associated with simulation. The CM File Manager includes a generic configuration management Application Program Interface (API) that can be adapted for the configuration management repositories of any U.S. engine company.

Federating LHCb datasets using the DIRAC File catalog

CERN Document Server

Haen, Christophe; Frank, Markus; Tsaregorodtsev, Andrei

2015-01-01

In the distributed computing model of LHCb the File Catalog (FC) is a central component that keeps track of each file and replica stored on the Grid. It is federating the LHCb data files in a logical namespace used by all LHCb applications. As a replica catalog, it is used for brokering jobs to sites where their input data is meant to be present, but also by jobs for finding alternative replicas if necessary. The LCG File Catalog (LFC) used originally by LHCb and other experiments is now being retired and needs to be replaced. The DIRAC File Catalog (DFC) was developed within the framework of the DIRAC Project and presented during CHEP 2012. From the technical point of view, the code powering the DFC follows an Aspect oriented programming (AOP): each type of entity that is manipulated by the DFC (Users, Files, Replicas, etc) is treated as a separate 'concern' in the AOP terminology. Hence, the database schema can also be adapted to the needs of a Virtual Organization. LHCb opted for a highly tuned MySQL datab...

File: International bilateral relations

International Nuclear Information System (INIS)

Feltin, Ch.; Rabouhams, J.; Bravo, X.; Rousseau, M.; Le Breton, S.; Saint Raymond, Ph.; Brigaud, O.; Pertuis, V.; McNair, J.; Sayers, M.R.; Bye, R.; Scherrer, J.

1998-01-01

Since its creation in 1973, the Authority of Safety was assigned missions in the international field with following objectives: to develop information exchanges with its foreign counterpart, to make know and to explain the French approach and practice; to give to concerned countries the useful information on french nuclear facilities situated near the border; This file shows with some examples, how bilateral relations allow to fill up these objectives and how the French Authority got the foreign experience. (N.C.)

Agent-Mining of Grid Log-Files: A Case Study

NARCIS (Netherlands)

Stoter, A.; Dalmolen, Simon; Mulder, .W.

2013-01-01

Grid monitoring requires analysis of large amounts of log files across multiple domains. An approach is described for automated extraction of job-flow information from large computer grids, using software agents and genetic computation. A prototype was created as a first step towards communities of

78 FR 47011 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Science.gov (United States)

2013-08-02

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Software Unit Testing for Digital Computer Software... revised regulatory guide (RG), revision 1 of RG 1.171, ``Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants.'' This RG endorses American National Standards...

77 FR 50722 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Science.gov (United States)

2012-08-22

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Software Unit Testing for Digital Computer Software...) is issuing for public comment draft regulatory guide (DG), DG-1208, ``Software Unit Testing for Digital Computer Software used in Safety Systems of Nuclear Power Plants.'' The DG-1208 is proposed...

EUMENES, a computer software for managing the radiation safety program information at an institutional level

International Nuclear Information System (INIS)

Hernandez Saiz, Alejandro; Cornejo Diaz, Nestor; Valdes Ramos, Maryzury; Martinez Gonzalez, Alina; Gonzalez Rodriguez, Niurka; Vergara Gil, Alex

2008-01-01

The correct application of national and international regulations in the field of Radiological Safety requires the implementation of Radiation Safety Programs appropriate to the developed practice. These Programs demand the preparation and keeping of an important number of records and data, the compliance with working schedules, systematic quality controls, audits, delivery of information to the Regulatory Authority, the execution of radiological assessments, etc. Therefore, it is unquestionable the necessity and importance of having a computer tool to support the management of the information related to the Radiation Safety Program in any institution. The present work describes a computer program that allows the efficient management of these data. Its design was based on the IAEA International Basic Safety Standards recommendations and on the requirements of the Cuban national standards, with the objective of being flexible enough to be applied in most of the institutions using ionizing radiations. The most important records of Radiation Safety Programs were incorporated and reports can be generated by the users. An additional tools-module allows the user to access to a radionuclide data library, and to carry out different calculations of interest in radiological protection. The program has been developed in Borland Delphi and manages Microsoft Access databases. It is a user friendly code that aims to support the optimization of Radiation Safety Programs. The program contributes to save resources and time, as the generated information is electronically kept and transmitted. The code has different security access levels according to the user responsibility at the institution and also provides for the analysis of the introduced data, in a quick and efficient way, as well as to notice deadlines, the exceeding of reference levels and situations that require attention. (author)

Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.

Energy Technology Data Exchange (ETDEWEB)

Carbajo, Juan (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin, Madison, WI); Schmidt, Rodney Cannon; Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Ludewig, Hans (Brookhaven National Laboratory, Upton, NY); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache %3CU%2B2013%3E CEA, France)

2011-06-01

This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the

Further computer appreciation

CERN Document Server

Fry, T F

2014-01-01

Further Computer Appreciation is a comprehensive cover of the principles and aspects in computer appreciation. The book starts by describing the development of computers from the first to the third computer generations, to the development of processors and storage systems, up to the present position of computers and future trends. The text tackles the basic elements, concepts and functions of digital computers, computer arithmetic, input media and devices, and computer output. The basic central processor functions, data storage and the organization of data by classification of computer files,

Grammar-Based Specification and Parsing of Binary File Formats

Directory of Open Access Journals (Sweden)

William Underwood

2012-03-01

Full Text Available The capability to validate and view or play binary file formats, as well as to convert binary file formats to standard or current file formats, is critically important to the preservation of digital data and records. This paper describes the extension of context-free grammars from strings to binary files. Binary files are arrays of data types, such as long and short integers, floating-point numbers and pointers, as well as characters. The concept of an attribute grammar is extended to these context-free array grammars. This attribute grammar has been used to define a number of chunk-based and directory-based binary file formats. A parser generator has been used with some of these grammars to generate syntax checkers (recognizers for validating binary file formats. Among the potential benefits of an attribute grammar-based approach to specification and parsing of binary file formats is that attribute grammars not only support format validation, but support generation of error messages during validation of format, validation of semantic constraints, attribute value extraction (characterization, generation of viewers or players for file formats, and conversion to current or standard file formats. The significance of these results is that with these extensions to core computer science concepts, traditional parser/compiler technologies can potentially be used as a part of a general, cost effective curation strategy for binary file formats.

A micro-computed tomographic evaluation of dentinal microcrack alterations during root canal preparation using single-file Ni-Ti systems.

Science.gov (United States)

Li, Mei-Lin; Liao, Wei-Li; Cai, Hua-Xiong

2018-01-01

The aim of the present study was to evaluate the length of dentinal microcracks observed prior to and following root canal preparation with different single-file nickel-titanium (Ni-Ti) systems using micro-computed tomography (micro-CT) analysis. A total of 80 mesial roots of mandibular first molars presenting with type II Vertucci canal configurations were scanned at an isotropic resolution of 7.4 µm. The samples were randomly assigned into four groups (n=20 per group) according to the system used for root canal preparation, including the WaveOne (WO), OneShape (OS), Reciproc (RE) and control groups. A second micro-CT scan was conducted after the root canals were prepared with size 25 instruments. Pre- and postoperative cross-section images of the roots (n=237,760) were then screened to identify the lengths of the microcracks. The results indicated that the microcrack lengths were notably increased following root canal preparation (Pfiles. Among the single-file Ni-Ti systems, WO and RE were not observed to cause notable microcracks, while the OS system resulted in evident microcracks.

Peregrine System | High-Performance Computing | NREL

Science.gov (United States)

classes of nodes that users access: Login Nodes Peregrine has four login nodes, each of which has Intel E5 /scratch file systems, the /mss file system is mounted on all login nodes. Compute Nodes Peregrine has 2592

BIBLIO: A Reprint File Management Algorithm

Science.gov (United States)

Zelnio, Robert N.; And Others

1977-01-01

The development of a simple computer algorithm designed for use by the individual educator or researcher in maintaining and searching reprint files is reported. Called BIBLIO, the system is inexpensive and easy to operate and maintain without sacrificing flexibility and utility. (LBH)

The NEA computer program library: a possible GDMS application

International Nuclear Information System (INIS)

Schuler, W.

1978-01-01

NEA Computer Program library maintains a series of eleven sequential computer files, used for linked applications in managing their stock of computer codes for nuclear reactor calculations, storing index and program abstract information, and administering their service to requesters. The high data redundancy beween the files suggests that a data base approach would be valid and this paper suggests a possible 'schema' for an CODASYL GDMS

78 FR 47015 - Software Requirement Specifications for Digital Computer Software Used in Safety Systems of...

Science.gov (United States)

2013-08-02

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Software Requirement Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission... issuing a revised regulatory guide (RG), revision 1 of RG 1.172, ``Software Requirement Specifications for...

Development of a script for converting DICOM files to .TXT

International Nuclear Information System (INIS)

Abrantes, Marcos E.S.; Oliveira, A.H. de

2014-01-01

Background: with the increased use of computer simulation techniques for diagnosis or therapy in patients, the MCNP and SCMS software is being widely used. For use as SCMS data entry interface for the MCNP is necessary to perform transformation of DICOM images to text files. Objective: to produce a semi automatic script conversion DICOM images generated by Computerized Tomography or Magnetic Resonance, for .txt in the IMAGEJ software. Methodology: this study was developed in the IMAGEJ software platform with an Intel Core 2 Duo computer, CPU of 2.00GHz, with 2:00 GB of RAM for 32-bit system. Development of the script was held in a text editor using JAVA language. For script insertion in IMAGEJ the plug in tool of this software was used. After this, a window is open asking for the path of the files that will be read, first and last name of DICOM file to be converted, along with where the new files will be stored. Results: for the manual processing of DICOM conversion to .txt of cerebral computed tomography with 600 images requires a time of about 8 hours. The use of script allows conversion time reduction for 12 minutes. Conclusion: the script used demonstrates DICOM conversion ability to .txt and a significant improvement in time savings in processing

The Development of Computer Code for Safety Injection Tank (SIT) with Fluidic Device(FD) Blowdown Test

International Nuclear Information System (INIS)

Lee, Joo Hee; Kim, Tae Han; Choi, Hae Yun; Lee, Kwang Won; Chung, Chang Kyu

2007-01-01

Safety Injection Tanks (SITs) with the Fluidic Device (FD) of APR1400 provides a means of rapid reflooding of the core following a large break Loss Of Coolant Accident (LOCA), and keeping it covered until flow from the Safety Injection Pump (SIP) becomes available. A passive FD can provide two operation stages of a safety water injection into the RCS and allow more effective use of borated water in case of LOCA. Once a large break LOCA occurs, the system will deliver a high flow rate of cooling water for a certain period of time, and thereafter, the flow rate is reduced to a lower flow rate. The conventional computer code 'TURTLE' used to simulate the blowdown of OPR1000 SIT can not be directly applied to simulate a blowdown process of the SIT with FD. A new computer code is needed to be developed for the blowdown test evaluation of the APR1400 SIT with FD. Korea Power Engineering Company (KOPEC) has developed a new computer code to analyze the characteristics of the SIT with FD and validated the code through the comparison of the calculation results with the test results obtained by Ulchin 5 and 6 units pre-operational test and VAlve Performance Evaluation Rig (VAPER) tests performed by The Korea Atomic Energy Research Institute (KAERI)

Network survivability performance (computer diskette)

Science.gov (United States)

1993-11-01

File characteristics: Data file; 1 file. Physical description: 1 computer diskette; 3 1/2 in.; high density; 2.0MB. System requirements: Mac; Word. This technical report has been developed to address the survivability of telecommunications networks including services. It responds to the need for a common understanding of, and assessment techniques for network survivability, availability, integrity, and reliability. It provides a basis for designing and operating telecommunication networks to user expectations for network survivability.

Development of data file system for cardiovascular nuclear medicine

International Nuclear Information System (INIS)

Hayashida, Kohei; Nishimura, Tsunehiko; Uehara, Toshiisa; Nisawa, Yoshifumi.

1985-01-01

A computer-assisted filing system for storing and processing data from cardiac pool scintigraphy and myocardial scintigraphy has been developed. Individual patient data are stored with his (her) identification number (ID) into floppy discs successively in order of receiving scintigraphy. Data for 900 patients can be stored per floppy disc. Scintigraphic findings can be outputted in a uniform file format, and can be used as a reporting format. Output or retrieval of filed individual patient data is possible according to each examination, disease code or ID. This system seems to be used for prospective study in patients with cardiovascular diseases. (Namekawa, K.)

Improved Flow Modeling in Transient Reactor Safety Analysis Computer Codes

International Nuclear Information System (INIS)

Holowach, M.J.; Hochreiter, L.E.; Cheung, F.B.

2002-01-01

A method of accounting for fluid-to-fluid shear in between calculational cells over a wide range of flow conditions envisioned in reactor safety studies has been developed such that it may be easily implemented into a computer code such as COBRA-TF for more detailed subchannel analysis. At a given nodal height in the calculational model, equivalent hydraulic diameters are determined for each specific calculational cell using either laminar or turbulent velocity profiles. The velocity profile may be determined from a separate CFD (Computational Fluid Dynamics) analysis, experimental data, or existing semi-empirical relationships. The equivalent hydraulic diameter is then applied to the wall drag force calculation so as to determine the appropriate equivalent fluid-to-fluid shear caused by the wall for each cell based on the input velocity profile. This means of assigning the shear to a specific cell is independent of the actual wetted perimeter and flow area for the calculational cell. The use of this equivalent hydraulic diameter for each cell within a calculational subchannel results in a representative velocity profile which can further increase the accuracy and detail of heat transfer and fluid flow modeling within the subchannel when utilizing a thermal hydraulics systems analysis computer code such as COBRA-TF. Utilizing COBRA-TF with the flow modeling enhancement results in increased accuracy for a coarse-mesh model without the significantly greater computational and time requirements of a full-scale 3D (three-dimensional) transient CFD calculation. (authors)

PWR hybrid computer model for assessing the safety implications of control systems

International Nuclear Information System (INIS)

Smith, O.L.; Renier, J.P.; Difilippo, F.C.; Clapp, N.E.; Sozer, A.; Booth, R.S.; Craddick, W.G.; Morris, D.G.

1986-03-01

The ORNL study of safety-related aspects of nuclear power plant control systems consists of two interrelated tasks: (1) failure mode and effects analysis (FMEA) that identified single and multiple component failures that might lead to significant plant upsets and (2) computer models that used these failures as initial conditions and traced the dynamic impact on the control system and remainder of the plant. This report describes the simulation of Oconee Unit 1, the first plant analyzed. A first-principles, best-estimate model was developed and implemented on a hybrid computer consisting of AD-4 analog and PDP-10 digital machines. Controls were placed primarily on the analog to use its interactive capability to simulate operator action. 48 refs., 138 figs., 15 tabs

Study and development of a document file system with selective access

International Nuclear Information System (INIS)

Mathieu, Jean-Claude

1974-01-01

The objective of this research thesis was to design and to develop a set of software aimed at an efficient management of a document file system by using methods of selective access to information. Thus, the three main aspects of file processing (creation, modification, reorganisation) have been addressed. The author first presents the main problems related to the development of a comprehensive automatic documentation system, and their conventional solutions. Some future aspects, notably dealing with the development of peripheral computer technology, are also evoked. He presents the characteristics of INIS bibliographic records provided by the IAEA which have been used to create the files. In the second part, he briefly describes the file system general organisation. This system is based on the use of two main files: an inverse file which contains for each descriptor a list of of numbers of files indexed by this descriptor, and a dictionary of descriptor or input file which gives access to the inverse file. The organisation of these both files is then describes in a detailed way. Other related or associated files are created, and the overall architecture and mechanisms integrated into the file data input software are described, as well as various processing applied to these different files. Performance and possible development are finally discussed

Computer-aided safety systems of industrial high energy objects

International Nuclear Information System (INIS)

Topolsky, N.G.; Gordeev, S.G.

1995-01-01

Modern objects of fuel and energy, chemical industries are characterized by high power consumption; by presence of large quantities of combustible and explosive substances used in technological processes; by advanced communications of submission systems of initial liquid and gasiform reagents, lubricants and coolants, the products of processing, and wastes of production; by advanced ventilation and pneumatic transport; and by complex control systems of energy, material and information flows. Such objects have advanced infrastructures, including a significant quantity of engineering buildings intended for storage, transportation, and processing of combustible liquids, gasiform fuels and materials, and firm materials. Examples of similar objects are nuclear and thermal power stations, chemical plants, machine-building factories, iron and steel industry enterprises, etc. Many tasks and functions characterizing the problem of fire safety of these objects can be accomplished only upon the development of special Computer-Aided Fire Safety Systems (CAFSS). The CAFSS for these objects are intended to reduce the hazard of disastrous accidents both causing fires and caused by them. The tasks of fire prevention and rescue work of large-scale industrial objects are analyzed within the bounds of the recommended conception. A functional structure of CAFSS with a list of the main subsystems forming a part of its composition has been proposed

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2009-03-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2010-10-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

International Nuclear Information System (INIS)

Schrader, Bradley J.

2009-01-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

An approach to the efficient assessment of safety and usability of computer based control systems, VeNuS 2. Global final report

International Nuclear Information System (INIS)

Nelke, T.; Dlugosch, C.; Olaverri Monreal, C.; Sachse, K.; Thuering, M.

2015-01-01

Prior to the use of computer-based instrumentation and control the evidence of sufficient safety, development methods and the suitability of man-machine interface must be provided. For this purpose, validation methods must be available, if possible supported by appropriate tools. Based on the multitude of the data which has to be taken into account it is important to generate technical documentation, to realize efficient operation and to prevent human based errors. An approach for computer based generation of user manuals for the operation of technical systems was developed in the VeNuS 2 project. A second goal was to develop an approach to evaluate the usability of safety relevant digital human-machine-interfaces (e.g. for nuclear industries). Therefore a software tool has been developed to assess aspects of usability of user interfaces by considering safety-related priorities. Additionally new or well known methods for provision of evidence of sufficient safety and usability for computer based systems shall be developed in a prototyped way.

Multi-level, automatic file management system using magnetic disk, mass storage system and magnetic tape

International Nuclear Information System (INIS)

Fujii, Minoru; Asai, Kiyoshi

1979-12-01

A simple, effective file management system using magnetic disk, mass storage system (MSS) and magnetic tape is described. Following are the concepts and techniques introduced in this file management system. (1) File distribution and continuity character of file references are closely approximated by memory retention function. A density function using the memory retention function is thus defined. (2) A method of computing the cost/benefit lines for magnetic disk, MSS and magnetic tape is presented. (3) A decision process of an optimal organization of file facilities incorporating file demands distribution to respective file devices, is presented. (4) A method of simple, practical, effective, automatic file management, incorporating multi-level file management, space management and file migration control, is proposed. (author)

FEDGROUP - A program system for producing group constants from evaluated nuclear data of files disseminated by IAEA

International Nuclear Information System (INIS)

Vertes, P.

1976-06-01

A program system for calculating group constants from several evaluated nuclear data files has been developed. These files are distributed by the Nuclear Data Section of IAEA. Our program system - FEDGROUP - has certain advantage over the well-known similar codes such as: 1. it requires only a medium sized computer />or approximately equal to 20000 words memory/, 2. it is easily adaptable to any type of computer, 3. it is flexible to the input evaluated nuclear data file and to the output group constant file. Nowadays, FEDGROUP calculates practically all types of group constants needed for reactor physics calculations by using the most frequent representations of evaluated data. (author)

The role of nuclear reaction theory and data in nuclear energy and safety applications

International Nuclear Information System (INIS)

Schmidt, J.J.

1993-01-01

The nuclear data requirements for nuclear fission reactor design and safety computations are so large that they cannot be satisfied by experimental measurements alone. Nuclear reaction theories and models have recently been developed and refined to the extent, that, with suitable parametrisation and fitting to accurately known experimental data, they can be used for filling gaps in the available experimental nuclear data base as well as for bulk computations of nuclear reaction, e.g. activation cross sections. The concurrent rapid development of ever more powerful mainframe and personal computers has stimulated the development of comprehensive nuclear model computer codes. A representative selection of such codes will be presented in the lectures and computer exercises of this Workshop. In order to fulfill nuclear data requirements of the nineties and, at the same time, develop improved tools for nuclear physics teaching at developing country universities it will be required and a major future task of the IAEA nuclear data programme to develop computer files of ''best'' sets of nuclear parameters for standardised input to nuclear model computations of nuclear data. Nuclear scientists from developing countries can make substantial contributions to this project. (author). 25 refs

ENDF/B-IV fission-product files: summary of major nuclide data

International Nuclear Information System (INIS)

England, T.R.; Schenter, R.E.

1975-09-01

The major fission-product parameters [sigma/sub th/, RI, tau/sub 1/2/, E-bar/sub β/, E-bar/sub γ/, E-bar/sub α/, decay and (n,γ) branching, Q, and AWR] abstracted from ENDF/B-IV files for 824 nuclides are summarized. These data are most often requested by users concerned with reactor design, reactor safety, dose, and other sundry studies. The few known file errors are corrected to date. Tabular data are listed by increasing mass number

Decay data file based on the ENSDF file

Energy Technology Data Exchange (ETDEWEB)

Katakura, J. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-03-01

A decay data file with the JENDL (Japanese Evaluated Nuclear Data Library) format based on the ENSDF (Evaluated Nuclear Structure Data File) file was produced as a tentative one of special purpose files of JENDL. The problem using the ENSDF file as primary source data of the JENDL decay data file is presented. (author)

KaZaA and similar Peer-to-Peer (P2P) file-sharing applications

CERN Multimedia

2003-01-01

Personal use of Peer-to-Peer (P2P) file sharing applications is NOT permitted at CERN. A non-exhaustive list of such applications, popular for exchanging music, videos, software etc, is: KaZaA, Napster, Gnutella, Edonkey2000, Napigator, Limewire, Bearshare, WinMX, Aimster, Morpheus, BitTorrent, ... You are reminded that use of CERN's Computing Facilities is governed by CERN's Computing Rules (Operational Circular No 5). They require that all users of CERN's Computing Facilities respect copyright, license and confidentiality agreements for data of any form (software, music, videos, etc). Sanctions are applicable in case of non-respect of the Computing Rules. Further details on restrictions for P2P applications are at: http://cern.ch/security/file-sharing CERN's Computing Rules are at: http://cern.ch/ComputingRules Denise Heagerty, CERN Computer Security Officer, Computer.Security@cern.ch

Grid collector an event catalog with automated file management

CERN Document Server

Ke Sheng Wu; Sim, A; Jun Min Gu; Shoshani, A

2004-01-01

High Energy Nuclear Physics (HENP) experiments such as STAR at BNL and ATLAS at CERN produce large amounts of data that are stored as files on mass storage systems in computer centers. In these files, the basic unit of data is an event. Analysis is typically performed on a selected set of events. The files containing these events have to be located, copied from mass storage systems to disks before analysis, and removed when no longer needed. These file management tasks are tedious and time consuming. Typically, all events contained in the files are read into memory before a selection is made. Since the time to read the events dominate the overall execution time, reading the unwanted event needlessly increases the analysis time. The Grid Collector is a set of software modules that works together to address these two issues. It automates the file management tasks and provides "direct" access to the selected events for analyses. It is currently integrated with the STAR analysis framework. The users can select ev...

A soft-contact model for computing safety margins in human prehension.

Science.gov (United States)

Singh, Tarkeshwar; Ambike, Satyajit

2017-10-01

The soft human digit tip forms contact with grasped objects over a finite area and applies a moment about an axis normal to the area. These moments are important for ensuring stability during precision grasping. However, the contribution of these moments to grasp stability is rarely investigated in prehension studies. The more popular hard-contact model assumes that the digits exert a force vector but no free moment on the grasped object. Many sensorimotor studies use this model and show that humans estimate friction coefficients to scale the normal force to grasp objects stably, i.e. the smoother the surface, the tighter the grasp. The difference between the applied normal force and the minimal normal force needed to prevent slipping is called safety margin and this index is widely used as a measure of grasp planning. Here, we define and quantify safety margin using a more realistic contact model that allows digits to apply both forces and moments. Specifically, we adapt a soft-contact model from robotics and demonstrate that the safety margin thus computed is a more accurate and robust index of grasp planning than its hard-contact variant. Previously, we have used the soft-contact model to propose two indices of grasp planning that show how humans account for the shape and inertial properties of an object. A soft-contact based safety margin offers complementary insights by quantifying how humans may account for surface properties of the object and skin tissue during grasp planning and execution. Copyright © 2017 Elsevier B.V. All rights reserved.

The version control service for the ATLAS data acquisition configuration files

International Nuclear Information System (INIS)

Soloviev, Igor

2012-01-01

The ATLAS experiment at the LHC in Geneva uses a complex and highly distributed Trigger and Data Acquisition system, involving a very large number of computing nodes and custom modules. The configuration of the system is specified by schema and data in more than 1000 XML files, with various experts responsible for updating the files associated with their components. Maintaining an error free and consistent set of XML files proved a major challenge. Therefore a special service was implemented; to validate any modifications; to check the authorization of anyone trying to modify a file; to record who had made changes, plus when and why; and to provide tools to compare different versions of files and to go back to earlier versions if required. This paper provides details of the implementation and exploitation experience, that may be interesting for other applications using many human-readable files maintained by different people, where consistency of the files and traceability of modifications are key requirements.

Competitive Status Signaling in Peer-to-Peer File-Sharing Networks

Directory of Open Access Journals (Sweden)

Henry F. Lyle

2007-04-01

Full Text Available Internet peer-to-peer file sharing is a contemporary example of asymmetrical sharing in which “altruists” (file uploaders share unconditionally with non-reciprocating “free riders” (file downloaders. Those who upload digital media files over the Internet risk prosecution for copyright infringement, and are more vulnerable to computer hackers and viruses. In an analysis of file-sharing behavior among university undergraduates (N=331, we found that significantly more males than females engaged in risky file uploading. Contrary to expectations, uploaders were not concerned about their reputation online and file sharers were not interested in identifying or chatting with uploaders while online. Among uploaders, males were more likely than females to be identified as uploaders by friends, to discuss uploading and to upload in the presence of peers. We interpret these results using costly-signaling theory, and argue that uploading is a costly signal in which males engage in avoidable risk taking as a means to compete for status among peers in social contexts other than the Internet.

Status of SACRD: a data base for fast reactor safety computer codes

International Nuclear Information System (INIS)

Greene, N.M.; Flanagan, G.F.; Alter, H.

1982-01-01

In 1975 work was initiated to provide a central computerized data collection of evaluated data for use in fast reactor safety computer codes. This data base is called SACRD and is intended to encompass handbook and other nonproblem-dependent data related to LMFBR's, especially at extreme conditions where little or no experimental data are available. Version 1 of the data base was released in the latter part of 1978 and remained the standard version until Version 81, which was released in October 1981

Testing the Forensic Interestingness of Image Files Based on Size and Type

Science.gov (United States)

2017-09-01

down to 0.18% (Rowe, 2015). 7 III. IMAGE FILE FORMATS When scanning a computer hard drive, many kinds of pictures are found. Digital images are not...3  III.  IMAGE FILE FORMATS ...Interchange Format JPEG Joint Photographic Experts Group LSH Locality Sensitive Hashing NSRL National Software Reference Library PDF Portable Document

OFFSCALE: PC input processor for SCALE-4 criticality sequences

International Nuclear Information System (INIS)

Bowman, S.M.

1991-01-01

OFFSCALE is a personal computer program that serves as a user-friendly interface for the Criticality Safety Analysis Sequences (CSAS) available in SCALE-4. It is designed to assist a SCALE-4 user in preparing an input file for execution of criticality safety problems. Output from OFFSCALE is a card-image input file that may be uploaded to a mainframe computer to execute the CSAS4 control module in SCALE-4. OFFSCALE features a pulldown menu system that accesses sophisticated data entry screens. The program allows the user to quickly set up a CSAS4 input file and perform data checking

Annual progress report FY 1977. [Computer calculations of light water reactor dynamics and safety

Energy Technology Data Exchange (ETDEWEB)

Hansen, K.F.; Henry, A.F.

1977-07-01

Progress is summarized in a project directed toward development of numerical methods suitable for the computer solution of problems in reactor dynamics and safety. Specific areas of research include methods of integration of the time-dependent diffusion equations by finite difference and finite element methods; representation of reactor properties by various homogenization procedures; application of synthesis methods; and development of response matrix techniques.

Overview and Status of the Ceph File System

CERN Multimedia

CERN. Geneva

2017-01-01

The Ceph file system (CephFS) is the POSIX-compatible distributed file system running on top of Ceph's powerful and stable object store. This presentation will give a general introduction of CephFS and detail the recent work the Ceph team has done to improve its stability and usability. In particular, we will cover directory fragmentation, multiple active metadata servers, and directory subtree pinning to metadata servers, features slated for stability in the imminent Luminous release. This talk will also give an overview of how we are measuring performance of multiple active metadata servers using large on-demand cloud deployments. The results will highlight how CephFS distributes metadata load across metadata servers to achieve scaling. About the speaker Patrick Donnelly is a software engineer at Red Hat, Inc. currently working on the Ceph distributed file system. In 2016 he completed his Ph.D. in computer science at the University of Notre Dame with a dissertation on the topic of file transfer management...

Tuning HDF5 subfiling performance on parallel file systems

Energy Technology Data Exchange (ETDEWEB)

Byna, Suren [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Chaarawi, Mohamad [Intel Corp. (United States); Koziol, Quincey [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Mainzer, John [The HDF Group (United States); Willmore, Frank [The HDF Group (United States)

2017-05-12

Subfiling is a technique used on parallel file systems to reduce locking and contention issues when multiple compute nodes interact with the same storage target node. Subfiling provides a compromise between the single shared file approach that instigates the lock contention problems on parallel file systems and having one file per process, which results in generating a massive and unmanageable number of files. In this paper, we evaluate and tune the performance of recently implemented subfiling feature in HDF5. In specific, we explain the implementation strategy of subfiling feature in HDF5, provide examples of using the feature, and evaluate and tune parallel I/O performance of this feature with parallel file systems of the Cray XC40 system at NERSC (Cori) that include a burst buffer storage and a Lustre disk-based storage. We also evaluate I/O performance on the Cray XC30 system, Edison, at NERSC. Our results show performance benefits of 1.2X to 6X performance advantage with subfiling compared to writing a single shared HDF5 file. We present our exploration of configurations, such as the number of subfiles and the number of Lustre storage targets to storing files, as optimization parameters to obtain superior I/O performance. Based on this exploration, we discuss recommendations for achieving good I/O performance as well as limitations with using the subfiling feature.

Quantitative software-reliability analysis of computer codes relevant to nuclear safety

International Nuclear Information System (INIS)

Mueller, C.J.

1981-12-01

This report presents the results of the first year of an ongoing research program to determine the probability of failure characteristics of computer codes relevant to nuclear safety. An introduction to both qualitative and quantitative aspects of nuclear software is given. A mathematical framework is presented which will enable the a priori prediction of the probability of failure characteristics of a code given the proper specification of its properties. The framework consists of four parts: (1) a classification system for software errors and code failures; (2) probabilistic modeling for selected reliability characteristics; (3) multivariate regression analyses to establish predictive relationships among reliability characteristics and generic code property and development parameters; and (4) the associated information base. Preliminary data of the type needed to support the modeling and the predictions of this program are described. Illustrations of the use of the modeling are given but the results so obtained, as well as all results of code failure probabilities presented herein, are based on data which at this point are preliminary, incomplete, and possibly non-representative of codes relevant to nuclear safety

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

Energy Technology Data Exchange (ETDEWEB)

Kirk, Bernadette Lugue [ORNL

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

Decryption-decompression of AES protected ZIP files on GPUs

Science.gov (United States)

Duong, Tan Nhat; Pham, Phong Hong; Nguyen, Duc Huu; Nguyen, Thuy Thanh; Le, Hung Duc

2011-10-01

AES is a strong encryption system, so decryption-decompression of AES encrypted ZIP files requires very large computing power and techniques of reducing the password space. This makes implementations of techniques on common computing system not practical. In [1], we reduced the original very large password search space to a much smaller one which surely containing the correct password. Based on reduced set of passwords, in this paper, we parallel decryption, decompression and plain text recognition for encrypted ZIP files by using CUDA computing technology on graphics cards GeForce GTX295 of NVIDIA, to find out the correct password. The experimental results have shown that the speed of decrypting, decompressing, recognizing plain text and finding out the original password increases about from 45 to 180 times (depends on the number of GPUs) compared to sequential execution on the Intel Core 2 Quad Q8400 2.66 GHz. These results have demonstrated the potential applicability of GPUs in this cryptanalysis field.

An asynchronous writing method for restart files in the gysela code in prevision of exascale systems*

Directory of Open Access Journals (Sweden)

Thomine O.

2013-12-01

Full Text Available The present work deals with an optimization procedure developed in the full-f global GYrokinetic SEmi-LAgrangian code (GYSELA. Optimizing the writing of the restart files is necessary to reduce the computing impact of crashes. These files require a very large memory space, and particularly so for very large mesh sizes. The limited bandwidth of the data pipe between the comput- ing nodes and the storage system induces a non-scalable part in the GYSELA code, which increases with the mesh size. Indeed the transfer time of RAM to data depends linearly on the files size. The necessity of non synchronized writing-in-file procedure is therefore crucial. A new GYSELA module has been developed. This asynchronous procedure allows the frequent writ- ing of the restart files, whilst preventing a severe slowing down due to the limited writing bandwidth. This method has been improved to generate a checksum control of the restart files, and automatically rerun the code in case of a crash for any cause.

Kepler Data Validation Time Series File: Description of File Format and Content

Science.gov (United States)

Mullally, Susan E.

2016-01-01

The Kepler space mission searches its time series data for periodic, transit-like signatures. The ephemerides of these events, called Threshold Crossing Events (TCEs), are reported in the TCE tables at the NASA Exoplanet Archive (NExScI). Those TCEs are then further evaluated to create planet candidates and populate the Kepler Objects of Interest (KOI) table, also hosted at the Exoplanet Archive. The search, evaluation and export of TCEs is performed by two pipeline modules, TPS (Transit Planet Search) and DV (Data Validation). TPS searches for the strongest, believable signal and then sends that information to DV to fit a transit model, compute various statistics, and remove the transit events so that the light curve can be searched for other TCEs. More on how this search is done and on the creation of the TCE table can be found in Tenenbaum et al. (2012), Seader et al. (2015), Jenkins (2002). For each star with at least one TCE, the pipeline exports a file that contains the light curves used by TPS and DV to find and evaluate the TCE(s). This document describes the content of these DV time series files, and this introduction provides a bit of context for how the data in these files are used by the pipeline.

Grid collector: An event catalog with automated file management

International Nuclear Information System (INIS)

Wu, Kesheng; Zhang, Wei-Ming; Sim, Alexander; Gu, Junmin; Shoshani, Arie

2003-01-01

High Energy Nuclear Physics (HENP) experiments such as STAR at BNL and ATLAS at CERN produce large amounts of data that are stored as files on mass storage systems in computer centers. In these files, the basic unit of data is an event. Analysis is typically performed on a selected set of events. The files containing these events have to be located, copied from mass storage systems to disks before analysis, and removed when no longer needed. These file management tasks are tedious and time consuming. Typically, all events contained in the files are read into memory before a selection is made. Since the time to read the events dominate the overall execution time, reading the unwanted event needlessly increases the analysis time. The Grid Collector is a set of software modules that works together to address these two issues. It automates the file management tasks and provides ''direct'' access to the selected events for analyses. It is currently integrated with the STAR analysis framework. The users can select events based on tags, such as, ''production date between March 10 and 20, and the number of charged tracks > 100.'' The Grid Collector locates the files containing relevant events, transfers the files across the Grid if necessary, and delivers the events to the analysis code through the familiar iterators. There has been some research efforts to address the file management issues, the Grid Collector is unique in that it addresses the event access issue together with the file management issues. This makes it more useful to a large variety of users

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

International Nuclear Information System (INIS)

Kirk, Bernadette Lugue

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries. An important activity of RSICC is its participation in international efforts on computational and experimental benchmarks. An example is the Shielding Integral Benchmarks Archival Database (SINBAD), which includes shielding benchmarks for fission, fusion and accelerators. RSICC is funded by the United States Department of Energy, Department of Homeland Security and Nuclear Regulatory Commission.

Reliable file sharing in distributed operating system using web RTC

Science.gov (United States)

Dukiya, Rajesh

2017-12-01

Since, the evolution of distributed operating system, distributed file system is come out to be important part in operating system. P2P is a reliable way in Distributed Operating System for file sharing. It was introduced in 1999, later it became a high research interest topic. Peer to Peer network is a type of network, where peers share network workload and other load related tasks. A P2P network can be a period of time connection, where a bunch of computers connected by a USB (Universal Serial Bus) port to transfer or enable disk sharing i.e. file sharing. Currently P2P requires special network that should be designed in P2P way. Nowadays, there is a big influence of browsers in our life. In this project we are going to study of file sharing mechanism in distributed operating system in web browsers, where we will try to find performance bottlenecks which our research will going to be an improvement in file sharing by performance and scalability in distributed file systems. Additionally, we will discuss the scope of Web Torrent file sharing and free-riding in peer to peer networks.

Status of the EU test blanket systems safety studies

International Nuclear Information System (INIS)

Panayotov, Dobromir; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-01-01

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

Status of the EU test blanket systems safety studies

Energy Technology Data Exchange (ETDEWEB)

Panayotov, Dobromir, E-mail: dobromir.panayotov@f4e.europa.eu; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-10-15

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

Nuclide identifier and grat data reader application for ORIGEN output file

International Nuclear Information System (INIS)

Arif Isnaeni

2011-01-01

ORIGEN is a one-group depletion and radioactive decay computer code developed at the Oak Ridge National Laboratory (ORNL). ORIGEN takes one-group neutronics calculation providing various nuclear material characteristics (the buildup, decay and processing of radioactive materials). ORIGEN output is a text-based file, ORIGEN output file contains only numbers in the form of group data nuclide, nuclide identifier and grat. This application was created to facilitate data collection nuclide identifier and grat, this application also has a function to acquire mass number data and calculate mass (gram) for each nuclide. Output from these applications can be used for computer code data input for neutronic calculations such as MCNP. (author)

The Fermilab central computing facility architectural model

International Nuclear Information System (INIS)

Nicholls, J.

1989-01-01

The goal of the current Central Computing Upgrade at Fermilab is to create a computing environment that maximizes total productivity, particularly for high energy physics analysis. The Computing Department and the Next Computer Acquisition Committee decided upon a model which includes five components: an interactive front-end, a Large-Scale Scientific Computer (LSSC, a mainframe computing engine), a microprocessor farm system, a file server, and workstations. With the exception of the file server, all segments of this model are currently in production: a VAX/VMS cluster interactive front-end, an Amdahl VM Computing engine, ACP farms, and (primarily) VMS workstations. This paper will discuss the implementation of the Fermilab Central Computing Facility Architectural Model. Implications for Code Management in such a heterogeneous environment, including issues such as modularity and centrality, will be considered. Special emphasis will be placed on connectivity and communications between the front-end, LSSC, and workstations, as practiced at Fermilab. (orig.)

The Fermilab Central Computing Facility architectural model

International Nuclear Information System (INIS)

Nicholls, J.

1989-05-01

The goal of the current Central Computing Upgrade at Fermilab is to create a computing environment that maximizes total productivity, particularly for high energy physics analysis. The Computing Department and the Next Computer Acquisition Committee decided upon a model which includes five components: an interactive front end, a Large-Scale Scientific Computer (LSSC, a mainframe computing engine), a microprocessor farm system, a file server, and workstations. With the exception of the file server, all segments of this model are currently in production: a VAX/VMS Cluster interactive front end, an Amdahl VM computing engine, ACP farms, and (primarily) VMS workstations. This presentation will discuss the implementation of the Fermilab Central Computing Facility Architectural Model. Implications for Code Management in such a heterogeneous environment, including issues such as modularity and centrality, will be considered. Special emphasis will be placed on connectivity and communications between the front-end, LSSC, and workstations, as practiced at Fermilab. 2 figs

Reactor Safety Assessment System

International Nuclear Information System (INIS)

Sebo, D.E.; Bray, M.A.; King, M.A.

1987-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSAS is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

Reactor safety assessment system

International Nuclear Information System (INIS)

Sebo, D.E.; Bray, M.A.; King, M.A.

1987-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSA is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

Computer managed emergency operating procedures

International Nuclear Information System (INIS)

Salamun, I.; Mavko, B.; Stritar, A.

1994-01-01

New computer technology is a very effective tool for developing a new design of nuclear power plant control room. It allows designer possibility to create a tool for managing with large database of power plant parameters and displaying them in different graphic forms and possibility of automated execution of well known task. The structure of Emergency Operating Procedures (EOP) is very suitable for programming and for creating expert system. The Computerized Emergency Operating Procedures (CEOP) described in this paper can be considered as an upgrading of standard EOP approach. EmDiSY (Emergency Display System - computer code name for CEOP) main purpose is to supply the operator with necessary information, to document all operator actions and to execute well known tasks. It is a function oriented CEOP that gives operator guidance on how to verify the critical safety functions and how to restore and maintain these functions where they are degraded. All knowledge is coded and stored in database files. The knowledge base consists from stepping order for verifying plant parameters, desired values of parameters, conditions for comparison and links between procedures and actions. Graphical shell allows users to read database, to follow instruction and to find out correct task. The desired information is concentrated in one screen and allows users to focus on a task. User is supported in two ways: desired parameter values are displayed on the process picture and automated monitoring critical safety function status trees are all time in progress and available to the user. (author). 4 refs, 4 figs

Outline of the requirements of application of computer based instrumentation and control systems in the systems important to safety on Bohunice NPPs

International Nuclear Information System (INIS)

Bacurik, J.

1997-01-01

The most important regulatory requirements and issues are described related to the review, evaluation and assessment of computer-based safety-related IandC systems, with emphasis on safety instrumentation and control. These aspects include safety classification and categorization of IandC, ranking of applicable codes and standards, design evaluation on the system level, and software assessment. (author)

OK, Computer: File Sharing, the Music Industry, and Why We Need the Pirate Party

Directory of Open Access Journals (Sweden)

Adrian Cosstick

2009-03-01

Full Text Available The Pirate Party believes the state and big business are in the process of protecting stale and inefficient models of business for their own monetary benefit by limiting our right to share information. The Pirate Party suggests that they are achieving this goal through the amendment of intellectual property legislation. In the dawn of the digital era, the Pirate Party advocates that governments and multinational corporations are using intellectual property to: crack down on file sharing which limits the ability to share knowledge and information; increase the terms and length of copyright to raise profits; and build code into music files which limits their ability to be shared (Pirate Party, 2009. There are a number of ‘copyright industries’ that are affected by these issues, none more so than the music industry. Its relationship with file sharing is topical and makes an excellent case study to address the impact big business has had on intellectual property and the need for the Pirate Party’s legislative input. The essay will then examine the central issues raised by illegal file sharing. In particular, the future for record companies in an environment that increasingly demands flexibility, and whether the Pirate Party’s proposal is a viable solution to the music industry’s problems

Accessing files in an Internet: The Jade file system

Science.gov (United States)

Peterson, Larry L.; Rao, Herman C.

1991-01-01

Jade is a new distribution file system that provides a uniform way to name and access files in an internet environment. It makes two important contributions. First, Jade is a logical system that integrates a heterogeneous collection of existing file systems, where heterogeneous means that the underlying file systems support different file access protocols. Jade is designed under the restriction that the underlying file system may not be modified. Second, rather than providing a global name space, Jade permits each user to define a private name space. These private name spaces support two novel features: they allow multiple file systems to be mounted under one directory, and they allow one logical name space to mount other logical name spaces. A prototype of the Jade File System was implemented on Sun Workstations running Unix. It consists of interfaces to the Unix file system, the Sun Network File System, the Andrew File System, and FTP. This paper motivates Jade's design, highlights several aspects of its implementation, and illustrates applications that can take advantage of its features.

Accessing files in an internet - The Jade file system

Science.gov (United States)

Rao, Herman C.; Peterson, Larry L.

1993-01-01

Jade is a new distribution file system that provides a uniform way to name and access files in an internet environment. It makes two important contributions. First, Jade is a logical system that integrates a heterogeneous collection of existing file systems, where heterogeneous means that the underlying file systems support different file access protocols. Jade is designed under the restriction that the underlying file system may not be modified. Second, rather than providing a global name space, Jade permits each user to define a private name space. These private name spaces support two novel features: they allow multiple file systems to be mounted under one directory, and they allow one logical name space to mount other logical name spaces. A prototype of the Jade File System was implemented on Sun Workstations running Unix. It consists of interfaces to the Unix file system, the Sun Network File System, the Andrew File System, and FTP. This paper motivates Jade's design, highlights several aspects of its implementation, and illustrates applications that can take advantage of its features.

Enkripsi dan Dekripsi File dengan Algoritma Blowfish pada Perangkat Mobile Berbasis Android

Directory of Open Access Journals (Sweden)

Siswo Wardoyo

2016-03-01

Full Text Available Cryptography is one of the ways used to secure data in the form of a file with encrypt files so that others are not entitled to know the file is private and confidential. One method is the algorithm Blowfish Cryptography which is a symmetric key using the algorithm to perform encryption and decryption. Applications that are built can perform file encryption-shaped images, videos, and documents. These applications can be running on a mobile phone that has a minimal operating system Android version 2.3. The software used to build these applications is Eclipse. The results of this research indicate that applications built capable of performing encryption and decryption. The results file encryption makes files into another unknown meaning. By using the keys numbered 72 bits or 9 character takes 1,49x108 years to break it with the speed it’s computation is 106 key/sec.

Strategies for Sharing Seismic Data Among Multiple Computer Platforms

Science.gov (United States)

Baker, L. M.; Fletcher, J. B.

2001-12-01

Seismic waveform data is readily available from a variety of sources, but it often comes in a distinct, instrument-specific data format. For example, data may be from portable seismographs, such as those made by Refraction Technology or Kinemetrics, from permanent seismograph arrays, such as the USGS Parkfield Dense Array, from public data centers, such as the IRIS Data Center, or from personal communication with other researchers through e-mail or ftp. A computer must be selected to import the data - usually whichever is the most suitable for reading the originating format. However, the computer best suited for a specific analysis may not be the same. When copies of the data are then made for analysis, a proliferation of copies of the same data results, in possibly incompatible, computer-specific formats. In addition, if an error is detected and corrected in one copy, or some other change is made, all the other copies must be updated to preserve their validity. Keeping track of what data is available, where it is located, and which copy is authoritative requires an effort that is easy to neglect. We solve this problem by importing waveform data to a shared network file server that is accessible to all our computers on our campus LAN. We use a Network Appliance file server running Sun's Network File System (NFS) software. Using an NFS client software package on each analysis computer, waveform data can then be read by our MatLab or Fortran applications without first copying the data. Since there is a single copy of the waveform data in a single location, the NFS file system hierarchy provides an implicit complete waveform data catalog and the single copy is inherently authoritative. Another part of our solution is to convert the original data into a blocked-binary format (known historically as USGS DR100 or VFBB format) that is interpreted by MatLab or Fortran library routines available on each computer so that the idiosyncrasies of each machine are not visible to

GIFT: an HEP project for file transfer

International Nuclear Information System (INIS)

Ferrer, M.L.; Mirabelli, G.; Valente, E.

1986-01-01

Started in autumn 1983, GIFT (General Internetwork File Transfer) is a collaboration among several HEP centers, including CERN, Frascati, Oslo, Oxford, RAL and Rome. The collaboration was initially set up with the aim of studying the feasibility of a software system to allow direct file exchange between computers which do not share a common Virtual File Protocol. After the completion of this first phase, an implementation phase started and, since March 1985, an experimental service based on this system has been running at CERN between DECnet, CERNET and the UK Coloured Book protocols. The authors present the motivations that, together with previous gateway experiences, led to the definition of GIFT specifications and to the implementation of the GIFT Kernel system. The position of GIFT in the overall development framework of the networking facilities needed by large international collaborations within the HEP community is explained. (Auth.)

77 FR 50724 - Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of...

Science.gov (United States)

2012-08-22

... review of applications for permits and licenses. The DG entitled ``Developing Software Life Cycle... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission...

FROM CAD MODEL TO 3D PRINT VIA “STL” FILE FORMAT

Directory of Open Access Journals (Sweden)

Cătălin IANCU

2010-06-01

Full Text Available The paper work presents the STL file format, which is now used for transferring information from CAD software to a 3D printer, for obtaining the solid model in Rapid prototyping and Computer Aided Manufacturing. It’s presented also the STL format structure, its history, limitations and further development, as well as its new version to arrive and other similar file formats. As a conclusion, STL files used to transfer data from CAD package to 3D printers has a series of limitations and therefore new formats will replace it soon.

Transmission of the environmental radiation data files on the internet

International Nuclear Information System (INIS)

Yamaguchi, Yoshiaki; Saito, Tadashi; Yamamoto, Takayoshi; Matsumoto, Atsushi; Kyoh, Bunkei

1999-01-01

Recently, any text or data file has come to be transportable through the Internet with a personal computer. It is, however, restricted by selection of monitoring point to lay the cable because the personal circuit is generally used in case of continuous type environmental monitors. This is the reason why we have developed an environmental monitoring system that can transmit radiation data files on the Internet. Both 3''φ x 3'' NaI(Tl) detector and Thermo-Hydrometer are installed in the monitoring post of this system, and the data files of those detectors are transmitted from a personal computer at the monitoring point to Radioisotope Research Center of Osaka University. Environmental monitoring data from remote places have easily been obtained due to the data transmission through the Internet. Moreover, the system brings a higher precision of the environmental monitoring data because it includes the energy information of γ-rays. If it is possible to maintain the monitors at remote places, this system could execute the continuous environmental monitoring over the wide area. (author)

Transmission of the environmental radiation data files on the internet

Energy Technology Data Exchange (ETDEWEB)

Yamaguchi, Yoshiaki; Saito, Tadashi; Yamamoto, Takayoshi [Osaka Univ., Suita (Japan). Radioisotope Research Center; Matsumoto, Atsushi; Kyoh, Bunkei

1999-01-01

Recently, any text or data file has come to be transportable through the Internet with a personal computer. It is, however, restricted by selection of monitoring point to lay the cable because the personal circuit is generally used in case of continuous type environmental monitors. This is the reason why we have developed an environmental monitoring system that can transmit radiation data files on the Internet. Both 3``{phi} x 3`` NaI(Tl) detector and Thermo-Hydrometer are installed in the monitoring post of this system, and the data files of those detectors are transmitted from a personal computer at the monitoring point to Radioisotope Research Center of Osaka University. Environmental monitoring data from remote places have easily been obtained due to the data transmission through the Internet. Moreover, the system brings a higher precision of the environmental monitoring data because it includes the energy information of {gamma}-rays. If it is possible to maintain the monitors at remote places, this system could execute the continuous environmental monitoring over the wide area. (author)

Nuclear safety: what is the price to pay? Press file

International Nuclear Information System (INIS)

Lheureux, Yves; Leclerc, Nathalie

2016-01-01

After having outlined that the ANCCLI's concern about French contradictions in the field of nuclear safety, this publication proposes an overview of the situation of nuclear safety in France in 2016 from the ANCCLI's point of view: big lessons and (too) small changes after Chernobyl and Fukushima, what has changed since Chernobyl and Fukushima. It outlines why emergency measures are not adapted according to the work of the joint ANCCLI-ACRO scientific committee. The following issues are thus commented: too many remaining questions, age and safety level of a nuclear plant, the specific intervention plans (PPI), sheltering, iodine distribution, population evacuation, evacuation time about nuclear sites, hosting sites in case of evacuation, refugees, safety and security. Recommendations are then given, based on European, Japanese, American, Canadian and Indian experiences. The project of a white paper on the post-accidental situation is presented. Several illustrations are proposed about some of the above issues

Grid collector: An event catalog with automated file management

Energy Technology Data Exchange (ETDEWEB)

Wu, Kesheng; Zhang, Wei-Ming; Sim, Alexander; Gu, Junmin; Shoshani, Arie

2003-10-17

High Energy Nuclear Physics (HENP) experiments such as STAR at BNL and ATLAS at CERN produce large amounts of data that are stored as files on mass storage systems in computer centers. In these files, the basic unit of data is an event. Analysis is typically performed on a selected set of events. The files containing these events have to be located, copied from mass storage systems to disks before analysis, and removed when no longer needed. These file management tasks are tedious and time consuming. Typically, all events contained in the files are read into memory before a selection is made. Since the time to read the events dominate the overall execution time, reading the unwanted event needlessly increases the analysis time. The Grid Collector is a set of software modules that works together to address these two issues. It automates the file management tasks and provides ''direct'' access to the selected events for analyses. It is currently integrated with the STAR analysis framework. The users can select events based on tags, such as, ''production date between March 10 and 20, and the number of charged tracks > 100.'' The Grid Collector locates the files containing relevant events, transfers the files across the Grid if necessary, and delivers the events to the analysis code through the familiar iterators. There has been some research efforts to address the file management issues, the Grid Collector is unique in that it addresses the event access issue together with the file management issues. This makes it more useful to a large variety of users.

Final Report for File System Support for Burst Buffers on HPC Systems

Energy Technology Data Exchange (ETDEWEB)

Yu, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mohror, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-11-27

Distributed burst buffers are a promising storage architecture for handling I/O workloads for exascale computing. As they are being deployed on more supercomputers, a file system that efficiently manages these burst buffers for fast I/O operations carries great consequence. Over the past year, FSU team has undertaken several efforts to design, prototype and evaluate distributed file systems for burst buffers on HPC systems. These include MetaKV: a Key-Value Store for Metadata Management of Distributed Burst Buffers, a user-level file system with multiple backends, and a specialized file system for large datasets of deep neural networks. Our progress for these respective efforts are elaborated further in this report.

Application of the defense-in-depth concept to qualify computer-based instrumentation and control systems important to safety

International Nuclear Information System (INIS)

Seidel, F.

1998-01-01

In parallel to the technological development, the authorities and expert organisations are preparing the application of computer-based I and C to NPPs from the regulatory point of view. Generally the associated world-wide procedure follows steps like identification of safety issues, completion of the regulatory framework particularly regarding the licensing requirements and furthermore, recommendation of an appropriate set of qualification methods to prove that the requirements are met. The paper's intention is to show from the regulatory point of view that the choice as well as the combination of the qualification methods depend on system design features and development strategy. Similar as for the safety system design required, a defense-in-depth qualification concept is suggested to be helpful in order to prove that the computer-based system meets the licensing requirements. (author)

Application of the defense-in-depth concept to qualify computer-based instrumentation and control systems important to safety

Energy Technology Data Exchange (ETDEWEB)

Seidel, F [Federal Office for Radiation Protection, Salzgitter (Germany)

1998-10-01

In parallel to the technological development, the authorities and expert organisations are preparing the application of computer-based I and C to NPPs from the regulatory point of view. Generally the associated world-wide procedure follows steps like identification of safety issues, completion of the regulatory framework particularly regarding the licensing requirements and furthermore, recommendation of an appropriate set of qualification methods to prove that the requirements are met. The paper`s intention is to show from the regulatory point of view that the choice as well as the combination of the qualification methods depend on system design features and development strategy. Similar as for the safety system design required, a defense-in-depth qualification concept is suggested to be helpful in order to prove that the computer-based system meets the licensing requirements. (author)

PWR hybrid computer model for assessing the safety implications of control systems

International Nuclear Information System (INIS)

Smith, O.L.; Booth, R.S.; Clapp, N.E.; DiFilippo, F.C.; Renier, J.P.; Sozer, A.

1985-01-01

The ORNL study of safety-related aspects of control systems consists of two interrelated tasks, (1) a failure mode and effects analysis that, in part, identifies single and multiple component failures that may lead to significant plant upsets, and (2) a hybrid computer model that uses these failures as initial conditions and traces the dynamic impact on the control system and remainder of the plant. The second task is reported here. The initial step in model development was to define a suitable interface between the FMEA and computer simulation tasks. This involved identifying primary plant components that must be simulated in dynamic detail and secondary components that can be treated adequately by the FMEA alone. The FMEA in general explores broader spectra of initiating events that may collapse into a reduced number of computer runs. A portion of the FMEA includes consideration of power supply failures. Consequences of the transients may feedback on the initiating causes, and there may be an interactive relationship between the FMEA and the computer simulation. Since the thrust of this program is to investigate control system behavior, the controls are modeled in detail to accurately reproduce characteristic response under normal and off-normal transients. The balance of the model, including neutronics, thermohydraulics and component submodels, is developed in sufficient detail to provide a suitable support for the control system

Characteristics of file sharing and peer to peer networking | Opara ...

African Journals Online (AJOL)

Characteristics of file sharing and peer to peer networking. ... distributing or providing access to digitally stored information, such as computer programs, ... including in multicast systems, anonymous communications systems, and web caches.

Adobe acrobat: an alternative electronic teaching file construction methodology independent of HTML restrictions.

Science.gov (United States)

Katzman, G L

2001-03-01

The goal of the project was to create a method by which an in-house digital teaching file could be constructed that was simple, inexpensive, independent of hypertext markup language (HTML) restrictions, and appears identical on multiple platforms. To accomplish this, Microsoft PowerPoint and Adobe Acrobat were used in succession to assemble digital teaching files in the Acrobat portable document file format. They were then verified to appear identically on computers running Windows, Macintosh Operating Systems (OS), and the Silicon Graphics Unix-based OS as either a free-standing file using Acrobat Reader software or from within a browser window using the Acrobat browser plug-in. This latter display method yields a file viewed through a browser window, yet remains independent of underlying HTML restrictions, which may confer an advantage over simple HTML teaching file construction. Thus, a hybrid of HTML-distributed Adobe Acrobat generated WWW documents may be a viable alternative for digital teaching file construction and distribution.

Nuclear structure data file. A manual for preparation of data sets

International Nuclear Information System (INIS)

Ewbank, W.B.; Schmorak, M.R.; Bertrand, F.E.; Feliciano, M.; Horen, D.J.

1975-06-01

The Nuclear Data Project at ORNL is building a computer-based file of nuclear structure data, which is intended for use by both basic and applied users. For every nucleus, the Nuclear Structure Data File contains evaluated nuclear structure information. This manual describes a standard input format for nuclear structure data. The format is sufficiently structured that bulk data can be entered efficiently. At the same time, the structure is open-ended and can accommodate most measured or deduced quantities that yield nuclear structure information. Computer programs have been developed at the Data Project to perform consistency checking and routine calculations. Programs are also used for preparing level scheme drawings. (U.S.)

Games that "work": using computer games to teach alcohol-affected children about fire and street safety.

Science.gov (United States)

Coles, Claire D; Strickland, Dorothy C; Padgett, Lynne; Bellmoff, Lynnae

2007-01-01

Unintentional injuries are a leading cause of death and disability for children. Those with developmental disabilities, including children affected by prenatal alcohol exposure, are at highest risk for injuries. Although teaching safety skills is recommended to prevent injury, cognitive limitations and behavioral problems characteristic of children with fetal alcohol spectrum disorder make teaching these skills challenging for parents and teachers. In the current study, 32 children, ages 4-10, diagnosed with fetal alcohol syndrome (FAS) and partial FAS, learned fire and street safety through computer games that employed "virtual worlds" to teach recommended safety skills. Children were pretested on verbal knowledge of four safety elements for both fire and street safety conditions and then randomly assigned to one condition. After playing the game until mastery, children were retested verbally and asked to "generalize" their newly acquired skills in a behavioral context. They were retested after 1 week follow-up. Children showed significantly better knowledge of the game to which they were exposed, immediately and at follow-up, and the majority (72%) was able to generalize all four steps within a behavioral setting. Results suggested that this is a highly effective method for teaching safety skills to high-risk children who have learning difficulties.

High School and Beyond Transcripts Survey (1982). Data File User's Manual. Contractor Report.

Science.gov (United States)

Jones, Calvin; And Others

This data file user's manual documents the procedures used to collect and process high school transcripts for a large sample of the younger cohort (1980 sophomores) in the High School and Beyond survey. The manual provides the user with the technical assistance needed to use the computer file and also discusses the following: (1) sample design for…

File structure and organization in the automation system for operative account of equipment and materials in JINR

International Nuclear Information System (INIS)

Gulyaeva, N.D.; Markova, N.F.; Nikitina, V.I.; Tentyukova, G.N.

1975-01-01

The structure and organization of files in the information bank for the first variant of a JINR material and technical supply subsystem are described. Automated system of equipment operative stock-taking on the base of the SDS-6200 computer is developed. Information is stored on magnetic discs. The arrangement of each file depends on its purpose and structure of data. Access to the files can be arbitrary or consecutive. The files are divided into groups: primary document files, long-term reference, information on items that may change as a result of administrative decision [ru

76 FR 10898 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

Science.gov (United States)

2011-02-28

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory..., Public Safety and Homeland Security Bureau, Federal Communications Commission, 445 12th Street, SW., Room..., Public Safety and Homeland Security Bureau. [FR Doc. 2011-4398 Filed 2-25-11; 8:45 am] BILLING CODE 6712...

Experimental Analysis of File Transfer Rates over Wide-Area Dedicated Connections

Energy Technology Data Exchange (ETDEWEB)

Rao, Nageswara S. [ORNL; Liu, Qiang [ORNL; Sen, Satyabrata [ORNL; Hinkel, Gregory Carl [ORNL; Imam, Neena [ORNL; Foster, Ian [University of Chicago; Kettimuthu, R. [Argonne National Laboratory (ANL); Settlemyer, Bradley [Los Alamos National Laboratory (LANL); Wu, Qishi [University of Memphis; Yun, Daqing [Harrisburg University

2016-12-01

File transfers over dedicated connections, supported by large parallel file systems, have become increasingly important in high-performance computing and big data workflows. It remains a challenge to achieve peak rates for such transfers due to the complexities of file I/O, host, and network transport subsystems, and equally importantly, their interactions. We present extensive measurements of disk-to-disk file transfers using Lustre and XFS file systems mounted on multi-core servers over a suite of 10 Gbps emulated connections with 0-366 ms round trip times. Our results indicate that large buffer sizes and many parallel flows do not always guarantee high transfer rates. Furthermore, large variations in the measured rates necessitate repeated measurements to ensure confidence in inferences based on them. We propose a new method to efficiently identify the optimal joint file I/O and network transport parameters using a small number of measurements. We show that for XFS and Lustre with direct I/O, this method identifies configurations achieving 97% of the peak transfer rate while probing only 12% of the parameter space.

Image Steganography of Multiple File Types with Encryption and Compression Algorithms

Directory of Open Access Journals (Sweden)

Ernest Andreigh C. Centina

2017-05-01

Full Text Available The goals of this study were to develop a system intended for securing files through the technique of image steganography integrated with cryptography by utilizing ZLIB Algorithm for compressing and decompressing secret files, DES Algorithm for encryption and decryption, and Least Significant Bit Algorithm for file embedding and extraction to avoid compromise on highly confidential files from exploits of unauthorized persons. Ensuing to this, the system is in acc ordance with ISO 9126 international quality standards. Every quality criteria of the system was evaluated by 10 Information Technology professionals, and the arithmetic Mean and Standard Deviation of the survey were computed. The result exhibits that m ost of them strongly agreed that the system is excellently effective based on Functionality, Reliability, Usability, Efficiency, Maintainability and Portability conformance to ISO 9126 standards. The system was found to be a useful tool for both governmen t agencies and private institutions for it could keep not only the message secret but also the existence of that particular message or file et maintaining the privacy of highly confidential and sensitive files from unauthorized access.

Database organization for computer-aided characterization of laser diode

International Nuclear Information System (INIS)

Oyedokun, Z.O.

1988-01-01

Computer-aided data logging involves a huge amount of data which must be properly managed for optimized storage space, easy access, retrieval and utilization. An organization method is developed to enhance the advantages of computer-based data logging of the testing of the semiconductor injection laser which optimize storage space, permit authorized user easy access and inhibits penetration. This method is based on unique file identification protocol tree structure and command file-oriented access procedures

Next generation WLCG File Transfer Service (FTS)

CERN Multimedia

CERN. Geneva

2012-01-01

LHC experiments at CERN and worldwide utilize WLCG resources and middleware components to perform distributed computing tasks. One of the most important tasks is reliable file replication. It is a complex problem, suffering from transfer failures, disconnections, transfer duplication, server and network overload, differences in storage systems, etc. To address these problems, EMI and gLite have provided the independent File Transfer Service (FTS) and Grid File Access Library (GFAL) tools. Their development started almost a decade ago, in the meantime, requirements in data management have changed - the old architecture of FTS and GFAL cannot keep support easily these changes. Technology has also been progressing: FTS and GFAL do not fit into the new paradigms (cloud, messaging, for example). To be able to serve the next stage of LHC data collecting (from 2013), we need a new generation of  these tools: FTS 3 and GFAL 2. We envision a service requiring minimal configuration, which can dynamically adapt to the...

Safety improvement plant modifications at Forsmark 3, 1986-1995

Energy Technology Data Exchange (ETDEWEB)

Kjellander, M. [Kaernkraftsaekerhet och utbildning, Nykoeping (Sweden)

1998-10-01

All important plant modifications implemented in safety-related equipment or software at Forsmark 3 are compiled in this report. The report covers the period from the start of commercial operation in 1985 up to and including 1995. The plant modifications, which were carried out by different suppliers during the guarantee period, are not included in the report since they have not been administered by the Forsmark organisation. The report contains references to relevant modification notices and to files and file divider numbers. These data refer to the Safety Department central archives. The report is based on Forsmark 3 Technical Specifications (STF) which means that Chapter 3 is divided into the same sections as in the STF. Modifications, which cannot be directly attributed to any specific STF chapter, and major modifications are described separately

A method to construct covariance files in ENDF/B format for criticality safety applications

International Nuclear Information System (INIS)

Naberejnev, D.G.; Smith, D.L.

1999-01-01

Argonne National Laboratory is providing support for a criticality safety analysis project that is being performed at Oak Ridge National Laboratory. The ANL role is to provide the covariance information needed by ORNL for this project. The ENDF/B-V evaluation is being used for this particular criticality analysis. In this evaluation, covariance information for several isotopes or elements of interest to this analysis is either not given or needs to be reconsidered. For some required materials, covariance information does not exist in ENDF/B-V: 233 U, 236 U, Zr, Mg, Gd, and Hf. For others, existing covariance information may need to be re-examined in light of the newer ENDF/B-V evaluation and recent experimental data. In this category are the following materials: 235 U, 238 U, 239 Pu, 240 Pu, 241 Pu, Fe, H, C, N, O, Al, Si, and B. A reasonable estimation of the fractional errors for various evaluated neutron cross sections from ENDF/B-V can be based on the comparisons between the major more recent evaluations including ENDF/B-VI, JENDL3.2, BROND2.2, and JEF2.2, as well as a careful examination of experimental data. A reasonable method to construct correlation matrices is proposed here. Coupling both of these considerations suggests a method to construct covariances files in ENDF/B format that can be used to express uncertainties for specific ENDF/B-V cross sections

Students "Hacking" School Computer Systems

Science.gov (United States)

Stover, Del

2005-01-01

This article deals with students hacking school computer systems. School districts are getting tough with students "hacking" into school computers to change grades, poke through files, or just pit their high-tech skills against district security. Dozens of students have been prosecuted recently under state laws on identity theft and unauthorized…

Computed Tomography (CT) -- Head

Medline Plus

Full Text Available ... Stroke Brain Tumors Computer Tomography (CT) Safety During Pregnancy Head and Neck Cancer X-ray, Interventional Radiology and Nuclear Medicine Radiation Safety Images related to Computed Tomography (CT) - ...

Development and design of a computer-assisted information management system for radiation safety management at the University of Washington

International Nuclear Information System (INIS)

Riches, C.G.; Riordan, F.J.; Robb, D.; Grieb, C.; Pence, G.; O'Brien, M.J.

1984-01-01

The Radiation Safety Office (RSO) at the University of Washington (UW) found that it needed a computerized information system to help manage the campus radiation safety program and to help provide the records necessary to show compliance with regulations and license requirements. The John L. Locke Computer Center at the UW had just developed the GLAMOR system to aid information entry and query for their computer when the RSO turned to them for assistance. The module that was developed provided a mechanism for controlling and monitoring radioactive materials on campus. This became one part of a multi-faceted system that registers users, employees, sealed sources and radiation-producing machines. The system is designed to be interactive, for immediate information recall, and powerful enough to provide routine and special reports on compliance status. The RSO information system is designed to be flexible and can easily incorporate additional features. Some future features include an interactive SNM control program, an interface to the information system currently being developed for the occupational safety and health program and an interface to the database provided by the commercial film badge service used by the University. Development of this program lead the RSO to appreciate the usefulness of having health physics professionals on the staff who were also knowledgeable about computers and who could develop programs and reports necessary to their activities

A History of the Andrew File System

CERN Multimedia

CERN. Geneva; Altman, Jeffrey

2011-01-01

Derrick Brashear and Jeffrey Altman will present a technical history of the evolution of Andrew File System starting with the early days of the Andrew Project at Carnegie Mellon through the commercialization by Transarc Corporation and IBM and a decade of OpenAFS. The talk will be technical with a focus on the various decisions and implementation trade-offs that were made over the course of AFS versions 1 through 4, the development of the Distributed Computing Environment Distributed File System (DCE DFS), and the course of the OpenAFS development community. The speakers will also discuss the various AFS branches developed at the University of Michigan, Massachusetts Institute of Technology and Carnegie Mellon University.

SIDS-toADF File Mapping Manual

Science.gov (United States)

McCarthy, Douglas; Smith, Matthew; Poirier, Diane; Smith, Charles A. (Technical Monitor)

2002-01-01

The "CFD General Notation System" (CGNS) consists of a collection of conventions, and conforming software, for the storage and retrieval of Computational Fluid Dynamics (CFD) data. It facilitates the exchange of data between sites and applications, and helps stabilize the archiving of aerodynamic data. This effort was initiated in order to streamline the procedures in exchanging data and software between NASA and its customers, but the goal is to develop CGNS into a National Standard for the exchange of aerodynamic data. The CGNS development team is comprised of members from Boeing Commercial Airplane Group, NASA-Ames, NASA-Langley, NASA-Lewis, McDonnell-Douglas Corporation (now Boeing-St. Louis), Air Force-Wright Lab., and ICEM-CFD Engineering. The elements of CGNS address all activities associated with the storage of data on external media and its movement to and from application programs. These elements include: 1) The Advanced Data Format (ADF) Database manager, consisting of both a file format specification and its I/O software, which handles the actual reading and writing of data from and to external storage media; 2) The Standard Interface Data Structures (SIDS), which specify the intellectual content of CFD data and the conventions governing naming and terminology; 3) The SIDS-to-ADF File Mapping conventions, which specify the exact location where the CFD data defined by the SIDS is to be stored within the ADF file(s); and 4) The CGNS Mid-level Library, which provides CFD-knowledgeable routines suitable for direct installation into application codes. The SIDS-toADF File Mapping Manual specifies the exact manner in which, under CGNS conventions, CFD data structures (the SIDS) are to be stored in (i.e., mapped onto) the file structure provided by the database manager (ADF). The result is a conforming CGNS database. Adherence to the mapping conventions guarantees uniform meaning and location of CFD data within ADF files, and thereby allows the construction of

Technical safety Organisations (TSO) contribute to European Nuclear Safety; Les organismes techniques de surete (TSO) au service de la surete nucleaire europeenne

Energy Technology Data Exchange (ETDEWEB)

Repussard, J. [Institut de radioprotection et de surete nucleaire - IRSN, 92 - Clarmart (France)

2010-11-15

Nuclear safety and radiation protection rely on science to achieve high level prevention objectives, through the analysis of safety files proposed by the licensees. The necessary expertise needs to be exercised so as to ensure adequate independence from nuclear operators, appropriate implementation of state of the art knowledge, and a broad spectrum of analysis, adequately ranking the positive and negative points of the safety files. The absence of a Europe-wide nuclear safety regime is extremely costly for an industry which has to cope with a highly competitive and open international environment, but has to comply with fragmented national regulatory systems. Harmonization is therefore critical, but such a goal is difficult to achieve. Only a gradual policy, made up of planned steps in each of the three key dimensions of the problem (energy policy at EU level, regulatory harmonization, consolidation of Europe-wide technical expertise capability) can be successful to achieve the required integration on the basis of the highest safety levels. TSO's contribute to this consolidation, with the support of the EC, in the fields of research (EURATOM-Programmes), of experience feedback analysis (European Clearinghouse), of training and knowledge management (European Training and Tutoring Institute, EUROSAFE). The TSO's network, ETSON, is becoming a formal organisation, able to enter into formal dialogue with EU institutions. However, nuclear safety nevertheless remains a world wide issue, requiring intensive international cooperation, including on TSO issues. (author)

Competency Reference for Computer Assisted Drafting.

Science.gov (United States)

Oregon State Dept. of Education, Salem. Div. of Vocational Technical Education.

This guide, developed in Oregon, lists competencies essential for students in computer-assisted drafting (CAD). Competencies are organized in eight categories: computer hardware, file usage and manipulation, basic drafting techniques, mechanical drafting, specialty disciplines, three dimensional drawing/design, plotting/printing, and advanced CAD.…

Distributed computing for FTU data handling

Energy Technology Data Exchange (ETDEWEB)

Bertocchi, A. E-mail: bertocchi@frascati.enea.it; Bracco, G.; Buceti, G.; Centioli, C.; Giovannozzi, E.; Iannone, F.; Panella, M.; Vitale, V

2002-06-01

The growth of data warehouse in tokamak experiment is leading fusion laboratories to provide new IT solutions in data handling. In the last three years, the Frascati Tokamak Upgrade (FTU) experimental database was migrated from IBM-mainframe to Unix distributed computing environment. The migration efforts have taken into account the following items: (1) a new data storage solution based on storage area network over fibre channel; (2) andrew file system (AFS) for wide area network file sharing; (3) 'one measure/one file' philosophy replacing 'one shot/one file' to provide a faster read/write data access; (4) more powerful services, such as AFS, CORBA and MDSplus to allow users to access FTU database from different clients, regardless their O.S.; (5) large availability of data analysis tools, from the locally developed utility SHOW to the multi-platform Matlab, interactive data language and jScope (all these tools are now able to access also the Joint European Torus data, in the framework of the remote data access activity); (6) a batch-computing cluster of Alpha/CompaqTru64 CPU based on CODINE/GRD to optimize utilization of software and hardware resources.

Use of computational fluid dynamics codes for safety analysis of nuclear reactor systems, including containment. Summary report of a technical meeting

International Nuclear Information System (INIS)

2003-11-01

Safety analysis is an important tool for justifying the safety of nuclear power plants. Typically, this type of analysis is performed by means of system computer codes with one dimensional approximation for modelling real plant systems. However, in the nuclear area there are issues for which traditional treatment using one dimensional system codes is considered inadequate for modelling local flow and heat transfer phenomena. There is therefore increasing interest in the application of three dimensional computational fluid dynamics (CFD) codes as a supplement to or in combination with system codes. There are a number of both commercial (general purpose) CFD codes as well as special codes for nuclear safety applications available. With further progress in safety analysis techniques, the increasing use of CFD codes for nuclear applications is expected. At present, the main objective with respect to CFD codes is generally to improve confidence in the available analysis tools and to achieve a more reliable approach to safety relevant issues. An exchange of views and experience can facilitate and speed up progress in the implementation of this objective. Both the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) believed that it would be advantageous to provide a forum for such an exchange. Therefore, within the framework of the Working Group on the Analysis and Management of Accidents of the NEA's Committee on the Safety of Nuclear Installations, the IAEA and the NEA agreed to jointly organize the Technical Meeting on the Use of Computational Fluid Dynamics Codes for Safety Analysis of Reactor Systems, including Containment. The meeting was held in Pisa, Italy, from 11 to 14 November 2002. The publication constitutes the report of the Technical Meeting. It includes short summaries of the presentations that were made and of the discussions as well as conclusions and

Input data requirements for special processors in the computation system containing the VENTURE neutronics code

International Nuclear Information System (INIS)

Vondy, D.R.; Fowler, T.B.; Cunningham, G.W.

1976-11-01

This report presents user input data requirements for certain special processors in a nuclear reactor computation system. These processors generally read data in formatted form and generate binary interface data files. Some data processing is done to convert from the user-oriented form to the interface file forms. The VENTURE diffusion theory neutronics code and other computation modules in this system use the interface data files which are generated

Input data requirements for special processors in the computation system containing the VENTURE neutronics code

International Nuclear Information System (INIS)

Vondy, D.R.; Fowler, T.B.; Cunningham, G.W.

1979-07-01

User input data requirements are presented for certain special processors in a nuclear reactor computation system. These processors generally read data in formatted form and generate binary interface data files. Some data processing is done to convert from the user oriented form to the interface file forms. The VENTURE diffusion theory neutronics code and other computation modules in this system use the interface data files which are generated

Safety evaluation of cosmetics in the EU. Reality and challenges for the toxicologist.

Science.gov (United States)

Pauwels, Marleen; Rogiers, Vera

2004-06-15

Council Directive 76/768/EEC, its seven amendments and 30 adaptations to technical progress form the basis of the cosmetic EU legislation today. There are actually four key principles for safety in the cosmetic legislation. (i) The full responsibility for the safety of cosmetics for human health is placed on the manufacturer, first importer in the EU or marketer. (ii) The safety evaluation of finished products is based on safety of individual ingredients, more specifically on their chemical structure, toxicological profile and their level of exposure. (iii) A compilation of information on each cosmetic product (dossier) must be kept readily available for inspection by the competent authorities of the Member State concerned. This information source, usually called a technical information file (TIF) or product information file/requirements (PIF(R)), contains, as the most important part, the safety assessment of the product undersigned by a competent safety assessor. (iv) The use of validated replacement alternative methods instead of animal testing forms the 4th key principle for safety of cosmetic products on the EU market. The 7th amendment imposes strict deadlines for the abolition of animal in vivo studies on cosmetic ingredients. These legal requirements induce a number of important challenges for the cosmetic industry and more specifically for the toxicologist involved as safety assessor.

The Fifth Workshop on HPC Best Practices: File Systems and Archives

Energy Technology Data Exchange (ETDEWEB)

Hick, Jason; Hules, John; Uselton, Andrew

2011-11-30

The workshop on High Performance Computing (HPC) Best Practices on File Systems and Archives was the fifth in a series sponsored jointly by the Department Of Energy (DOE) Office of Science and DOE National Nuclear Security Administration. The workshop gathered technical and management experts for operations of HPC file systems and archives from around the world. Attendees identified and discussed best practices in use at their facilities, and documented findings for the DOE and HPC community in this report.

In vitro comparative evaluation of cleaning efficacy and volumetric filling in primary molars: Cone beam computed tomography evaluation

Directory of Open Access Journals (Sweden)

Anshula Neeraj Deshpande

2017-01-01

Full Text Available Introduction: Pulpectomy of primary teeth is mostly carried out with hand files and broaches which is tricky and time consuming procedure. The development of new design features like varying tapers, non-cutting safety tips and varying length of cutting blades have resulted in new generation of rotary instruments. Aim: To compare and evaluate cleaning efficacy, canal preparation and volumetric filling using conventional files and rotary V Taper files through cone beam computed tomography. Materials and Method: Thirty extracted primary molars were selected. The teeth were randomly divided into three groups each containing 10 teeth i.e. 30 canals in each group. Group A was instrumented with K files; Group B rotary V Taper files and Group C was Hybrid group. Sodium hypochlorite (1% was used for irrigation. Root canal filling was done with Zinc Oxide Eugenol cement in all groups. The volumetric analysis i.e. Percentage of Volume (POV of the root canal filling in primary molars was done through CBCT Software. Result: In present study, p- value was found to be significant (<0.05. Almost 100% of canals of hybrid group were fully filled and 63.3% of canals of hand filing group were partially filled. The filling was found to be dense and no. of voids was least in hybrid group. Conclusion: Clinical time required in primary molar endodontics, especially with unpredictability and difficulty of canal morphology, is inevitable. The study confirms superior ability of rotary-file systems to shape severely curved canals with less time and significant decrease in procedural errors like partial filling, voids and inappropriate canal preparation.

Electronic licensing filing system development and implementation experience

International Nuclear Information System (INIS)

Walderhaug, J.

1993-01-01

The Electronic Licensing Filing System (ELFS) is a microcomputer-based integrated document search and retrieval system for the Nuclear Regulatory Affairs Division of Southern California Edison (SCE). ELFS allows the user access to the current licensing basis of a subject by providing an easily searchable electronic information data base consisting of regulatory correspondence, design-bases documentation, licensing documents [updated final safety and analysis report (UFSAR) and technical specifications], and regulatory guidance or directives [10CFR, generic letters, bulletins, notices, circulars, regulatory guides, policy statements, and selected US Nuclear Regulatory Commission (NRC) regulations]. It is used in the preparation of correspondence and submittals to the NRC, 50.59 safety evaluations, design-bases reconstitution, and commitment tracking and management

45 CFR 1356.30 - Safety requirements for foster care and adoptive home providers.

Science.gov (United States)

2010-10-01

... licensing file for that foster or adoptive family must contain documentation which verifies that safety... 45 Public Welfare 4 2010-10-01 2010-10-01 false Safety requirements for foster care and adoptive... ON CHILDREN, YOUTH AND FAMILIES, FOSTER CARE MAINTENANCE PAYMENTS, ADOPTION ASSISTANCE, AND CHILD AND...

Ordinance concerning the filing of transport of nuclear fuel materials

International Nuclear Information System (INIS)

1979-01-01

The ordinance is defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the order for execution of the law. Any person who reports the transport of nuclear fuel materials shall file four copies of a notification according to the form attached to the public safety commission of the prefecture in charge of the dispatching place. When the transportation extends over the area in charge of another public safety commission, the commission which has received the notice shall report without delay date and route of the transport, kind and quantity of nuclear fuel materials and other necessary matters to the commission concerned and hear from the latter opinions on the items informed. The designation by the ordinance includes speed of the vehicle loaded with nuclear fuel materials, disposition of an accompanying car, arrangement of the line of the loaded vehicle and accompanying and other escorting cars, location of the parking, place of unloading and temporary storage, etc. Reports concerning troubles and measures taken shall be filed in ten days to the public safety commission which has received the notification, when accidents occur on the way, such as: theft or loss of nuclear fuel materials; traffic accident; irregular leaking of nuclear fuel materials and personal trouble by the transport. (Okada, K.)

JENDL special purpose file

International Nuclear Information System (INIS)

Nakagawa, Tsuneo

1995-01-01

In JENDL-3,2, the data on all the reactions having significant cross section over the neutron energy from 0.01 meV to 20 MeV are given for 340 nuclides. The object range of application extends widely, such as the neutron engineering, shield and others of fast reactors, thermal neutron reactors and nuclear fusion reactors. This is a general purpose data file. On the contrary to this, the file in which only the data required for a specific application field are collected is called special purpose file. The file for dosimetry is a typical special purpose file. The Nuclear Data Center, Japan Atomic Energy Research Institute, is making ten kinds of JENDL special purpose files. The files, of which the working groups of Sigma Committee are in charge, are listed. As to the format of the files, ENDF format is used similarly to JENDL-3,2. Dosimetry file, activation cross section file, (α, n) reaction data file, fusion file, actinoid file, high energy data file, photonuclear data file, PKA/KERMA file, gas production cross section file and decay data file are described on their contents, the course of development and their verification. Dosimetry file and gas production cross section file have been completed already. As for the others, the expected time of completion is shown. When these files are completed, they are opened to the public. (K.I.)

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

International Nuclear Information System (INIS)

Lhomme, Veronique; Daubard, Jean-Paul

2013-01-01

of safety file (safety options file, general operating rules, on site emergency plan, periodic safety review documents, incident analysis...). In each chapter, the aforesaid Parts 1, 2 and 3 are developed. A first draft of the guide was published in March 2010 for use by assessment's teams of IRSN, and to obtain an operational feedback to improve it. Beyond that, the guide is also intended to be, on the topic of safety assessment for the fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management, a tool for tutoring (inside and outside the IRSN) and a reference to make available, outside of the IRSN, the approach of expertise and the 'know-how' of IRSN. In this context, the IRSN's methodology of assessment regarding 'criticality' and 'fire' have been put online, on the IRSN's web site. The paper presents the purpose and the structure of the guide and its interest for the safety assessment of fuel cycle facilities; in this frame, the chapters 'Assessment of the risk from handling operations' and 'Assessment of the periodic safety review documents' are presented in details as illustrations. It gives also information about its others uses. (authors)

Nuclear safety - Topical issues

International Nuclear Information System (INIS)

1995-01-01

The following topical issues related to nuclear safety are discussed: steam generators; maintenance strategies; control rod drive nozzle cracks; core shrouds cracks; sump strainer blockage; fire protection; computer software important for safety; safety during shutdown; operational safety experience; external hazards and other site related issues. 5 figs, 5 tabs

Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

1997-01-01

This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

Report on nuclear industry quality assurance procedures for safety analysis computer code development and use

International Nuclear Information System (INIS)

Sheron, B.W.; Rosztoczy, Z.R.

1980-08-01

As a result of a request from Commissioner V. Gilinsky to investigate in detail the causes of an error discovered in a vendor Emergency Core Cooling System (ECCS) computer code in March, 1978, the staff undertook an extensive investigation of the vendor quality assurance practices applied to safety analysis computer code development and use. This investigation included inspections of code development and use practices of the four major Light Water Reactor Nuclear Steam Supply System vendors and a major reload fuel supplier. The conclusion reached by the staff as a result of the investigation is that vendor practices for code development and use are basically sound. A number of areas were identified, however, where improvements to existing vendor procedures should be made. In addition, the investigation also addressed the quality assurance (QA) review and inspection process for computer codes and identified areas for improvement

A lightweight high availability strategy for Atlas LCG File Catalogs

International Nuclear Information System (INIS)

Martelli, Barbara; Salvo, Alessandro de; Anzellotti, Daniela; Rinaldi, Lorenzo; Cavalli, Alessandro; Pra, Stefano dal; Dell'Agnello, Luca; Gregori, Daniele; Prosperini, Andrea; Ricci, Pier Paolo; Sapunenko, Vladimir

2010-01-01

The LCG File Catalog is a key component of the LHC Computing Grid middleware [1], as it contains the mapping between Logical File Names and Physical File Names on the Grid. The Atlas computing model foresees multiple local LFC housed in each Tier-1 and Tier-0, containing all information about files stored in the regional cloud. As the local LFC contents are presently not replicated anywhere, this turns out in a dangerous single point of failure for all of the Atlas regional clouds. In order to solve this problem we propose a novel solution for high availability (HA) of Oracle based Grid services, obtained by composing an Oracle Data Guard deployment and a series of application level scripts. This approach has the advantage of being very easy to deploy and maintain, and represents a good candidate solution for all Tier-2s which are usually little centres with little manpower dedicated to service operations. We also present the results of a wide range of functionality and performance tests run on a test-bed having characteristics similar to the ones required for production. The test-bed consists of a failover deployment between the Italian LHC Tier-1 (INFN - CNAF) and an Atlas Tier-2 located at INFN - Roma1. Moreover, we explain how the proposed strategy can be deployed on the present Grid infrastructure, without requiring any change to the middleware and in a way that is totally transparent to end users and applications.

Teaching, Learning, and Collaborating in the Cloud: Applications of Cloud Computing for Educators in Post-Secondary Institutions

Science.gov (United States)

Aaron, Lynn S.; Roche, Catherine M.

2012-01-01

"Cloud computing" refers to the use of computing resources on the Internet instead of on individual personal computers. The field is expanding and has significant potential value for educators. This is discussed with a focus on four main functions: file storage, file synchronization, document creation, and collaboration--each of which has…

Publication and Retrieval of Computational Chemical-Physical Data Via the Semantic Web. Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Ostlund, Neil [Chemical Semantics, Inc., Gainesville, FL (United States)

2017-07-20

This research showed the feasibility of applying the concepts of the Semantic Web to Computation Chemistry. We have created the first web portal (www.chemsem.com) that allows data created in the calculations of quantum chemistry, and other such chemistry calculations to be placed on the web in a way that makes the data accessible to scientists in a semantic form never before possible. The semantic web nature of the portal allows data to be searched, found, and used as an advance over the usual approach of a relational database. The semantic data on our portal has the nature of a Giant Global Graph (GGG) that can be easily merged with related data and searched globally via a SPARQL Protocol and RDF Query Language (SPARQL) that makes global searches for data easier than with traditional methods. Our Semantic Web Portal requires that the data be understood by a computer and hence defined by an ontology (vocabulary). This ontology is used by the computer in understanding the data. We have created such an ontology for computational chemistry (purl.org/gc) that encapsulates a broad knowledge of the field of computational chemistry. We refer to this ontology as the Gainesville Core. While it is perhaps the first ontology for computational chemistry and is used by our portal, it is only a start of what must be a long multi-partner effort to define computational chemistry. In conjunction with the above efforts we have defined a new potential file standard (Common Standard for eXchange – CSX for computational chemistry data). This CSX file is the precursor of data in the Resource Description Framework (RDF) form that the semantic web requires. Our portal translates CSX files (as well as other computational chemistry data files) into RDF files that are part of the graph database that the semantic web employs. We propose a CSX file as a convenient way to encapsulate computational chemistry data.

11 CFR 100.19 - File, filed or filing (2 U.S.C. 434(a)).

Science.gov (United States)

2010-01-01

... a facsimile machine or by electronic mail if the reporting entity is not required to file..., including electronic reporting entities, may use the Commission's website's on-line program to file 48-hour... the reporting entity is not required to file electronically in accordance with 11 CFR 104.18. [67 FR...

Storage of sparse files using parallel log-structured file system

Science.gov (United States)

Bent, John M.; Faibish, Sorin; Grider, Gary; Torres, Aaron

2017-11-07

A sparse file is stored without holes by storing a data portion of the sparse file using a parallel log-structured file system; and generating an index entry for the data portion, the index entry comprising a logical offset, physical offset and length of the data portion. The holes can be restored to the sparse file upon a reading of the sparse file. The data portion can be stored at a logical end of the sparse file. Additional storage efficiency can optionally be achieved by (i) detecting a write pattern for a plurality of the data portions and generating a single patterned index entry for the plurality of the patterned data portions; and/or (ii) storing the patterned index entries for a plurality of the sparse files in a single directory, wherein each entry in the single directory comprises an identifier of a corresponding sparse file.

Green light for the methodology file. Periodical safety review 2016 has begun

International Nuclear Information System (INIS)

2014-01-01

Every ten years, the organisational framework and the facilities of the Belgian Nuclear Research Center SCK-CEN are subject to an encompassing safety evaluation. Together with initiatives arising from the stress tests, a large number of safety studies and actions are scheduled until 2018. The article discusses the ongoing safety review.

Benchmarking and monitoring framework for interconnected file synchronization and sharing services

DEFF Research Database (Denmark)

Mrówczyński, Piotr; Mościcki, Jakub T.; Lamanna, Massimo

2018-01-01

computing and storage infrastructure in the research labs. In this work we present a benchmarking and monitoring framework for file synchronization and sharing services. It allows service providers to monitor the operational status of their services, understand the service behavior under different load...... types and with different network locations of the synchronization clients. The framework is designed as a monitoring and benchmarking tool to provide performance and robustness metrics for interconnected file synchronization and sharing services such as Open Cloud Mesh....

SFR Safety Considerations

International Nuclear Information System (INIS)

Glatz, Jean-Paul

2012-01-01

Objectives of the Safety and Operation Project: • analysis and experiments that support approaches and assess performance of specific safety features, • development and verification of computational tools and validation of models employed in safety assessment and facility licensing, and • valorisation of reactor operation, from experience and testing in operating SFR plants

Translator program converts computer printout into braille language

Science.gov (United States)

Powell, R. A.

1967-01-01

Computer program converts print image tape files into six dot Braille cells, enabling a blind computer programmer to monitor and evaluate data generated by his own programs. The Braille output is printed 8 lines per inch.

Optimized distributed systems achieve significant performance improvement on sorted merging of massive VCF files.

Science.gov (United States)

Sun, Xiaobo; Gao, Jingjing; Jin, Peng; Eng, Celeste; Burchard, Esteban G; Beaty, Terri H; Ruczinski, Ingo; Mathias, Rasika A; Barnes, Kathleen; Wang, Fusheng; Qin, Zhaohui S

2018-06-01

Sorted merging of genomic data is a common data operation necessary in many sequencing-based studies. It involves sorting and merging genomic data from different subjects by their genomic locations. In particular, merging a large number of variant call format (VCF) files is frequently required in large-scale whole-genome sequencing or whole-exome sequencing projects. Traditional single-machine based methods become increasingly inefficient when processing large numbers of files due to the excessive computation time and Input/Output bottleneck. Distributed systems and more recent cloud-based systems offer an attractive solution. However, carefully designed and optimized workflow patterns and execution plans (schemas) are required to take full advantage of the increased computing power while overcoming bottlenecks to achieve high performance. In this study, we custom-design optimized schemas for three Apache big data platforms, Hadoop (MapReduce), HBase, and Spark, to perform sorted merging of a large number of VCF files. These schemas all adopt the divide-and-conquer strategy to split the merging job into sequential phases/stages consisting of subtasks that are conquered in an ordered, parallel, and bottleneck-free way. In two illustrating examples, we test the performance of our schemas on merging multiple VCF files into either a single TPED or a single VCF file, which are benchmarked with the traditional single/parallel multiway-merge methods, message passing interface (MPI)-based high-performance computing (HPC) implementation, and the popular VCFTools. Our experiments suggest all three schemas either deliver a significant improvement in efficiency or render much better strong and weak scalabilities over traditional methods. Our findings provide generalized scalable schemas for performing sorted merging on genetics and genomics data using these Apache distributed systems.

Cut-and-Paste file-systems: integrating simulators and file systems

NARCIS (Netherlands)

Bosch, H.G.P.; Mullender, Sape J.

1995-01-01

We have implemented an integrated and configurable file system called the Pegasus filesystem (PFS) and a trace-driven file-system simulator called Patsy. Patsy is used for off-line analysis of file-systemalgorithms, PFS is used for on-line file-systemdata storage. Algorithms are first analyzed in

Qualification of integrated tool environments (QUITE) for the development of computer-based safety systems in NPP

International Nuclear Information System (INIS)

Miedl, Horst

2004-01-01

In NPP I et C systems are back fitted meanwhile increasingly by computer-based systems (I et C platforms). The corresponding safety functions are implemented by software, and this software is developed, configured and administrated with the help of integrated tool environments (ITE). An ITE offers a set of services which are used to construct an I et C system and consist typically of software packages for project control and documentation, specification and design, automatic code generation and so on. Commercial ITE are not necessarily conceived and qualified (type-tested) for nuclear specific applications but are used - and will increasingly be used - for the implementation of nuclear safety related I et C systems. Therefor, it is necessary to qualify commercial ITE with respect to their influence on the quality of the target system for each I et C platform (dependent on the safety category of the target system). Examples for commercial ITEs are I et C platforms like SPINLINE 3, TELEPERM XP, Common Q, TRICON, etc. (Author)

Cluster computing software for GATE simulations

International Nuclear Information System (INIS)

Beenhouwer, Jan de; Staelens, Steven; Kruecker, Dirk; Ferrer, Ludovic; D'Asseler, Yves; Lemahieu, Ignace; Rannou, Fernando R.

2007-01-01

Geometry and tracking (GEANT4) is a Monte Carlo package designed for high energy physics experiments. It is used as the basis layer for Monte Carlo simulations of nuclear medicine acquisition systems in GEANT4 Application for Tomographic Emission (GATE). GATE allows the user to realistically model experiments using accurate physics models and time synchronization for detector movement through a script language contained in a macro file. The downside of this high accuracy is long computation time. This paper describes a platform independent computing approach for running GATE simulations on a cluster of computers in order to reduce the overall simulation time. Our software automatically creates fully resolved, nonparametrized macros accompanied with an on-the-fly generated cluster specific submit file used to launch the simulations. The scalability of GATE simulations on a cluster is investigated for two imaging modalities, positron emission tomography (PET) and single photon emission computed tomography (SPECT). Due to a higher sensitivity, PET simulations are characterized by relatively high data output rates that create rather large output files. SPECT simulations, on the other hand, have lower data output rates but require a long collimator setup time. Both of these characteristics hamper scalability as a function of the number of CPUs. The scalability of PET simulations is improved here by the development of a fast output merger. The scalability of SPECT simulations is improved by greatly reducing the collimator setup time. Accordingly, these two new developments result in higher scalability for both PET and SPECT simulations and reduce the computation time to more practical values

77 FR 34457 - Pipeline Safety: Mechanical Fitting Failure Reports

Science.gov (United States)

2012-06-11

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... notice provides clarification to owners and operators of gas distribution pipeline facilities when... of a gas distribution pipeline facility to file a written report for any mechanical fitting failure...

Safety Performance Improvement for Nuclear Power Plants Utilizing THOMAS

International Nuclear Information System (INIS)

Kim, Won June; Ryu, Jung Uk; Suh, Kune Y.

2005-01-01

THOMAS (Thermal Hydraulics Online Monitoring Advisory System) is equipped with a couple of salient features compared with existing monitoring systems. The first has to do with the three-dimensional (3D) visualization technique to support the nuclear power plant (NPP) operators and personnel using the virtual reality (VR) technology. VR depicts an environment simulated by a computer. Most of the VR environments primarily include visual experiences, displayed either on a monitor or though special stereoscopic goggles. Users can often interactively manipulate a VR environment, either through standard input devices like a keyboard, or through specially designed devices like a cybergloves. Additional devices were not applied the in THOMAS. The visualized model file is brought to the VR space from the computer-aided design (CAD) tool. In the VR space, using mapping, the component color is changed with linked value of the safety variables. Operators thus can easily recognize the plant condition. This is related with the human factor engineering. The second is the function of decision making using the influence diagram logic. The influence diagram logic is based on the total probability and Bayesian theory. The accident modeling is rooted in the emergency operating procedure (EOP). The final goal of this system is, in the accident situation, to present a success path to the operator for the recovery of the NPP system. At the current developing level, the database signals THOMAS. In other words, a spectrum of system analysis codes provides the safety parameter values to the database, which are subsequently supplied to THOMAS through the network

Cut-and-Paste file-systems : integrating simulators and file systems

NARCIS (Netherlands)

Bosch, H.G.P.; Mullender, Sape J.

1996-01-01

We have implemented an integrated and configurable file system called the PFS and a trace-driven file-system simulator called Patsy. Patsy is used for off-line analysis of file-system algorithms, PFS is used for on-line file-system data storage. Algorithms are first analyzed in Patsy and when we are

Computer stress study of bone with computed tomography

International Nuclear Information System (INIS)

Linden, M.J.; Marom, S.A.; Linden, C.N.

1986-01-01

A computer processing tool has been developed which, together with a finite element program, determines the stress-deformation pattern in a long bone, utilizing Computed Tomography (CT) data files for the geometry and radiographic density information. The geometry, together with mechanical properties and boundary conditions: loads and displacements, comprise the input of the Finite element (FE) computer program. The output of the program is the stresses and deformations in the bone. The processor is capable of developing an accurate three-dimensional finite element model from a scanned human long bone due to the CT high pixel resolution and the local mechanical properties determined from the radiographic densities of the scanned bone. The processor, together with the finite element program, serves first as an analysis tool towards improved understanding of bone function and remodelling. In this first stage, actual long bones may be scanned and analyzed under applied loads and displacements, determined from existing gait analyses. The stress-deformation patterns thus obtained may be used for studying the biomechanical behavior of particular long bones such as bones with implants and with osteoporosis. As a second stage, this processor may serve as a diagnostic tool for analyzing the biomechanical response of a specific patient's long long bone under applied loading by utilizing a CT data file of the specific bone as an input to the processor with the FE program

Interactive computer codes for education and training on nuclear safety and radioprotection

International Nuclear Information System (INIS)

Leszczynski, Francisco

2008-01-01

Two interactive computer codes for education and training on nuclear safety and radioprotection developed at RA6 Reactor Division-Bariloche Atomic Center-CNEA are presented on this paper. The first code named SIMREACT has been developed in order to simulate the control of a research nuclear reactor in real time with a simple but accurate approach. The code solves the equations of neutron punctual kinetics with time variable reactivity. Utilizing the timer of the computer and the controls of a PC keyboard, with an adequate graphic interface, a simulation in real time of the temporal behavior of a research reactor is obtained. The reactivity can be changed by means of the extraction or insertion of control rods. It was implemented also the simulation of automatic pilot and scram. The use of this code is focalized on practices of nuclear reactor control like start-up from the subcritical state with external source up to power to a desired level, change of power level, calibration of a control rod with different methods, and approach to critical condition by interpolation of the answer in function of reactivity. The second code named LICEN has been developed in order to help the studies of all the topics included in examination programs for obtaining licenses for research reactor operators and radioprotection officials. Using the PC mouse, with an adequate graphic interface, the student can gradually learn the topics related with general and special licenses. The general option includes nuclear reactor engineering, radioprotection, nuclear safety, documentation and normative. The specific option includes mandatory documentation, description of the installation and task on normal and emergency situations. For each of these topics there are sub-items with all the relevant information. The objective of this code is to joint in one electronic place a large amount of information which usually it is disseminated on difficult to find separated papers. (author)

Computed micro-tomographic evaluation of glide path with nickel-titanium rotary PathFile in maxillary first molars curved canals.

Science.gov (United States)

Pasqualini, Damiano; Bianchi, Caterina Chiara; Paolino, Davide Salvatore; Mancini, Lucia; Cemenasco, Andrea; Cantatore, Giuseppe; Castellucci, Arnaldo; Berutti, Elio

2012-03-01

X-ray computed micro-tomography scanning allows high-resolution 3-dimensional imaging of small objects. In this study, micro-CT scanning was used to compare the ability of manual and mechanical glide path to maintain the original root canal anatomy. Eight extracted upper first permanent molars were scanned at the TOMOLAB station at ELETTRA Synchrotron Light Laboratory in Trieste, Italy, with a microfocus cone-beam geometry system. A total of 2,400 projections on 360° have been acquired at 100 kV and 80 μA, with a focal spot size of 8 μm. Buccal root canals of each specimen (n = 16) were randomly assigned to PathFile (P) or stainless-steel K-file (K) to perform glide path at the full working length. Specimens were then microscanned at the apical level (A) and at the point of the maximum curvature level (C) for post-treatment analyses. Curvatures of root canals were classified as moderate (≤35°) or severe (≥40°). The ratio of diameter ratios (RDRs) and the ratio of cross-sectional areas (RAs) were assessed. For each level of analysis (A and C), 2 balanced 2-way factorial analyses of variance (P < .05) were performed to evaluate the significance of the instrument factor and of canal curvature factor as well as the interactions of the factors both with RDRs and RAs. Specimens in the K group had a mean curvature of 35.4° ± 11.5°; those in the P group had a curvature of 38° ± 9.9°. The instrument factor (P and K) was extremely significant (P < .001) for both the RDR and RA parameters, regardless of the point of analysis. Micro-CT scanning confirmed that NiTi rotary PathFile instruments preserve the original canal anatomy and cause less canal aberrations. Copyright © 2012 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

Computational fluid dynamic simulation of pressurizer safety valve loop seal purge phenomena in nuclear power plants

International Nuclear Information System (INIS)

Park, Jong Woon

2012-01-01

In Korean 3 Loop plants a water loop seal pipe is installed containing condensed water upstream of a pressurizer safety valve to protect the valve disk from the hot steam environment. The loop seal water purge time is a key parameter in safety analyses for overpressure transients, because it delays valve opening. The loop seal purge time is uncertain to measure by test and thus 3-dimensional realistic computational fluid dynamics (CFD) model is developed in this paper to predict the seal water purge time before full opening of the valve which is driven by steam after water purge. The CFD model for a typical pressurizer safety valve with a loop seal pipe is developed using the computer code of ANSYS CFX 11. Steady-state simulations are performed for full discharge of steam at the valve full opening. Transient simulations are performed for the loop seal dynamics and to estimate the loop seal purge time. A sudden pressure drop higher than 2,000 psia at the tip of the upper nozzle ring is expected from the steady-state calculation. Through the transient simulation, almost loop seal water is discharged within 1.2 second through the narrow opening between the disk and the nozzle of the valve. It can be expected that the valve fully opens at least before 1.2 second because constant valve opening is assumed in this CFX simulation, which is conservative because the valve opens fully before the loop seal water is completely discharged. The predicted loop seal purge time is compared with previous correlation. (orig.)

Computational fluid dynamic simulation of pressurizer safety valve loop seal purge phenomena in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Park, Jong Woon [Dongguk Univ., Gyeongju (Korea, Republic of). Nuclear and Energy Engineering Dept.

2012-11-15

In Korean 3 Loop plants a water loop seal pipe is installed containing condensed water upstream of a pressurizer safety valve to protect the valve disk from the hot steam environment. The loop seal water purge time is a key parameter in safety analyses for overpressure transients, because it delays valve opening. The loop seal purge time is uncertain to measure by test and thus 3-dimensional realistic computational fluid dynamics (CFD) model is developed in this paper to predict the seal water purge time before full opening of the valve which is driven by steam after water purge. The CFD model for a typical pressurizer safety valve with a loop seal pipe is developed using the computer code of ANSYS CFX 11. Steady-state simulations are performed for full discharge of steam at the valve full opening. Transient simulations are performed for the loop seal dynamics and to estimate the loop seal purge time. A sudden pressure drop higher than 2,000 psia at the tip of the upper nozzle ring is expected from the steady-state calculation. Through the transient simulation, almost loop seal water is discharged within 1.2 second through the narrow opening between the disk and the nozzle of the valve. It can be expected that the valve fully opens at least before 1.2 second because constant valve opening is assumed in this CFX simulation, which is conservative because the valve opens fully before the loop seal water is completely discharged. The predicted loop seal purge time is compared with previous correlation. (orig.)

Research on the improvement of nuclear safety

International Nuclear Information System (INIS)

Yoo, Keon Joong; Kim, Dong Soo; Kim, Hui Dong; Park, Chang Kyu

1993-06-01

To improve the nuclear safety, this project is divided into three areas which are the development of safety analysis technology, the development of severe accident analysis technology and the development of integrated safety assessment technology. 1. The development of safety analysis technology. The present research aims at the development of necessary technologies for nuclear safety analysis in Korea. Establishment of the safety analysis technologies enables to reduce the expenditure both by eliminating excessive conservatisms incorporated in nuclear reactor design and by increasing safety margins in operation. It also contributes to improving plant safety through realistic analyses of the Emergency Operating Procedures (EOP). 2. The development of severe accident analysis technology. By the computer codes (MELCOR and CONTAIN), the in-vessel and the ex-vessel severe accident phenomena are simulated. 3. The development of integrated safety assessment technology. In the development of integrated safety assessment techniques, the included research areas are the improvement of PSA computer codes, the basic study on the methodology for human reliability analysis (HRA) and common cause failure (CCF). For the development of the level 2 PSA computer code, the basic research for the interface between level 1 and 2 PSA, the methodology for the treatment of containment event tree are performed. Also the new technologies such as artificial intelligence, object-oriented programming techniques are used for the improvement of computer code and the assessment techniques

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation

International Nuclear Information System (INIS)

1997-03-01

This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U.S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system was born. This manual covers an array of modules written for the SCALE package, consisting of drivers, system libraries, cross section and materials properties libraries, input/output routines, storage modules, and help files

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U.S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system was born. This manual covers an array of modules written for the SCALE package, consisting of drivers, system libraries, cross section and materials properties libraries, input/output routines, storage modules, and help files.

Operating and maintenance experience with computer-based systems in nuclear power plants - A report by the PWG-1 Task Group on Computer-based Systems Important to Safety

International Nuclear Information System (INIS)

1998-01-01

This report was prepared by the Task Group on Computer-based Systems Important to Safety of the Principal Working Group No. 1. Canada had a leading role in this study. Operating and Maintenance Experience with Computer-based Systems in nuclear power plants is essential for improving and upgrading against potential failures. The present report summarises the observations and findings related to the use of digital technology in nuclear power plants. It also makes recommendations for future activities in Member Countries. Continued expansion of digital technology in nuclear power reactor has resulted in new safety and licensing issues, since the existing licensing review criteria were mainly based on the analogue devices used when the plants were designed. On the industry side, a consensus approach is needed to help stabilise and standardise the treatment of digital installations and upgrades while ensuring safety and reliability. On the regulatory side, new guidelines and regulatory requirements are needed to assess digital upgrades. Upgrades or new installation issues always involve potential for system failures. They are addressed specifically in the 'hazard' or 'failure' analysis, and it is in this context that they ultimately are resolved in the design and addressed in licensing. Failure Analysis is normally performed in parallel with the design, verification and validation (V and V), and implementation activities of the upgrades. Current standards and guidelines in France, U.S. and Canada recognise the importance of failure analysis in computer-based system design. Thus failure analysis is an integral part of the design and implementation process and is aimed at evaluating potential failure modes and cause of system failures. In this context, it is essential to define 'System' as the plant system affected by the upgrade, not the 'Computer' system. The identified failures would provide input to the design process in the form of design requirements or design

Cloud Computing: Architecture and Services

OpenAIRE

Ms. Ravneet Kaur

2018-01-01

Cloud computing is Internet-based computing, whereby shared resources, software, and information are provided to computers and other devices on demand, like the electricity grid. It is a method for delivering information technology (IT) services where resources are retrieved from the Internet through web-based tools and applications, as opposed to a direct connection to a server. Rather than keeping files on a proprietary hard drive or local storage device, cloud-based storage makes it possib...

EVALUATED NUCLEAR STRUCTURE DATA FILE. A MANUAL FOR PREPARATION OF DATA SETS

International Nuclear Information System (INIS)

TULI, J.K.

2001-01-01

This manual describes the organization and structure of the Evaluated Nuclear Structure Data File (ENSDF). This computer-based file is maintained by the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory for the international Nuclear Structure and Decay Data Network. For every mass number (presently, A ≤ 293), the Evaluated Nuclear Structure Data File (ENSDF) contains evaluated structure information. For masses A ≥ 44, this information is published in the Nuclear Data Sheets; for A < 44, ENSDF is based on compilations published in the journal Nuclear Physics. The information in ENSDF is updated by mass chain or by nuclide with a varying cycle time dependent on the availability of new information

File sharing

NARCIS (Netherlands)

van Eijk, N.

2011-01-01

‘File sharing’ has become generally accepted on the Internet. Users share files for downloading music, films, games, software etc. In this note, we have a closer look at the definition of file sharing, the legal and policy-based context as well as enforcement issues. The economic and cultural

A convertor and user interface to import CAD files into worldtoolkit virtual reality systems

Science.gov (United States)

Wang, Peter Hor-Ching

1996-01-01

Virtual Reality (VR) is a rapidly developing human-to-computer interface technology. VR can be considered as a three-dimensional computer-generated Virtual World (VW) which can sense particular aspects of a user's behavior, allow the user to manipulate the objects interactively, and render the VW at real-time accordingly. The user is totally immersed in the virtual world and feel the sense of transforming into that VW. NASA/MSFC Computer Application Virtual Environments (CAVE) has been developing the space-related VR applications since 1990. The VR systems in CAVE lab are based on VPL RB2 system which consists of a VPL RB2 control tower, an LX eyephone, an Isotrak polhemus sensor, two Fastrak polhemus sensors, a folk of Bird sensor, and two VPL DG2 DataGloves. A dynamics animator called Body Electric from VPL is used as the control system to interface with all the input/output devices and to provide the network communications as well as VR programming environment. The RB2 Swivel 3D is used as the modelling program to construct the VW's. A severe limitation of the VPL VR system is the use of RB2 Swivel 3D, which restricts the files to a maximum of 1020 objects and doesn't have the advanced graphics texture mapping. The other limitation is that the VPL VR system is a turn-key system which does not provide the flexibility for user to add new sensors and C language interface. Recently, NASA/MSFC CAVE lab provides VR systems built on Sense8 WorldToolKit (WTK) which is a C library for creating VR development environments. WTK provides device drivers for most of the sensors and eyephones available on the VR market. WTK accepts several CAD file formats, such as Sense8 Neutral File Format, AutoCAD DXF and 3D Studio file format, Wave Front OBJ file format, VideoScape GEO file format, Intergraph EMS stereolithographics and CATIA Stereolithographics STL file formats. WTK functions are object-oriented in their naming convention, are grouped into classes, and provide easy C

Digital Stratigraphy: Contextual Analysis of File System Traces in Forensic Science.

Science.gov (United States)

Casey, Eoghan

2017-12-28

This work introduces novel methods for conducting forensic analysis of file allocation traces, collectively called digital stratigraphy. These in-depth forensic analysis methods can provide insight into the origin, composition, distribution, and time frame of strata within storage media. Using case examples and empirical studies, this paper illuminates the successes, challenges, and limitations of digital stratigraphy. This study also shows how understanding file allocation methods can provide insight into concealment activities and how real-world computer usage can complicate digital stratigraphy. Furthermore, this work explains how forensic analysts have misinterpreted traces of normal file system behavior as indications of concealment activities. This work raises awareness of the value of taking the overall context into account when analyzing file system traces. This work calls for further research in this area and for forensic tools to provide necessary information for such contextual analysis, such as highlighting mass deletion, mass copying, and potential backdating. © 2017 American Academy of Forensic Sciences.

COMBINE archive and OMEX format: one file to share all information to reproduce a modeling project.

Science.gov (United States)

Bergmann, Frank T; Adams, Richard; Moodie, Stuart; Cooper, Jonathan; Glont, Mihai; Golebiewski, Martin; Hucka, Michael; Laibe, Camille; Miller, Andrew K; Nickerson, David P; Olivier, Brett G; Rodriguez, Nicolas; Sauro, Herbert M; Scharm, Martin; Soiland-Reyes, Stian; Waltemath, Dagmar; Yvon, Florent; Le Novère, Nicolas

2014-12-14

With the ever increasing use of computational models in the biosciences, the need to share models and reproduce the results of published studies efficiently and easily is becoming more important. To this end, various standards have been proposed that can be used to describe models, simulations, data or other essential information in a consistent fashion. These constitute various separate components required to reproduce a given published scientific result. We describe the Open Modeling EXchange format (OMEX). Together with the use of other standard formats from the Computational Modeling in Biology Network (COMBINE), OMEX is the basis of the COMBINE Archive, a single file that supports the exchange of all the information necessary for a modeling and simulation experiment in biology. An OMEX file is a ZIP container that includes a manifest file, listing the content of the archive, an optional metadata file adding information about the archive and its content, and the files describing the model. The content of a COMBINE Archive consists of files encoded in COMBINE standards whenever possible, but may include additional files defined by an Internet Media Type. Several tools that support the COMBINE Archive are available, either as independent libraries or embedded in modeling software. The COMBINE Archive facilitates the reproduction of modeling and simulation experiments in biology by embedding all the relevant information in one file. Having all the information stored and exchanged at once also helps in building activity logs and audit trails. We anticipate that the COMBINE Archive will become a significant help for modellers, as the domain moves to larger, more complex experiments such as multi-scale models of organs, digital organisms, and bioengineering.

Temperature increases on the external root surface during endodontic treatment using single file systems.

Science.gov (United States)

Özkocak, I; Taşkan, M M; Gökt Rk, H; Aytac, F; Karaarslan, E Şirin

2015-01-01

The aim of this study is to evaluate increases in temperature on the external root surface during endodontic treatment with different rotary systems. Fifty human mandibular incisors with a single root canal were selected. All root canals were instrumented using a size 20 Hedstrom file, and the canals were irrigated with 5% sodium hypochlorite solution. The samples were randomly divided into the following three groups of 15 teeth: Group 1: The OneShape Endodontic File no.: 25; Group 2: The Reciproc Endodontic File no.: 25; Group 3: The WaveOne Endodontic File no.: 25. During the preparation, the temperature changes were measured in the middle third of the roots using a noncontact infrared thermometer. The temperature data were transferred from the thermometer to the computer and were observed graphically. Statistical analysis was performed using the Kruskal-Wallis analysis of variance at a significance level of 0.05. The increases in temperature caused by the OneShape file system were lower than those of the other files (P file showed the highest temperature increases. However, there were no significant differences between the Reciproc and WaveOne files. The single file rotary systems used in this study may be recommended for clinical use.

From files to SAF: 3D endodontic treatment is possible at last.

Science.gov (United States)

Metzger, Zvi

2011-01-01

3D cleaning, shaping and obturation of root canals has always been the desired goal of endodontic treatment which in many cases is difficult to attain. The introduction of NiTi rotary files made a major change in endodontic practice, making treatment easier, safer and faster. Nevertheless, after 16 years of intensive development, most of these instruments still share several drawbacks, the major one being the inability to three-dimensionally clean and shape oval root canals. The Self-Adjusting File (SAF) System was designed to overcome many of the current drawbacks of rotary file systems. It is based on a hollow, highly compressible file that adapts itself three-dimensionally to the shape of a given root canal, including its cross section. The file is operated with vibratory in-and-out motion, with continuous irrigation delivered by a peristaltic pump through the hollow file. A uniform layer of dentin is removed from the whole circumference of the root canal, thus achieving the main goals of root canal treatment while preserving the remaining root dentin. The 3D scrubbing effect of the file, combined with the always fresh irrigant, result in unprecedentedly clean canals which facilitate in turn better obturation. More effective disinfection of flat-oval root canals is another goal which is simultaneously attained. The safety of the root-canal treatment is also greatly enhanced by the high mechanical stability of the SAF and by using a new concept of no-pressure irrigation. The SAF System gets the operator much closer to the long-desired goal of 3D root-canal treatment.

75 FR 33696 - Safety Zone: July Firework Display in Captain of the Port, Puget Sound AOR

Science.gov (United States)

2010-06-15

...-AA00 Safety Zone: July Firework Display in Captain of the Port, Puget Sound AOR AGENCY: Coast Guard... Captain of the Port, Puget Sound AOR. (a) Safety Zone. The following area is a designated safety zone: all..., Captain of the Port, Puget Sound. [FR Doc. 2010-14294 Filed 6-14-10; 8:45 am] BILLING CODE 9110-04-P ...

State of the art of computer codes and experimental investigations on safety of nuclear power plants with reactors of WWER type

International Nuclear Information System (INIS)

Asmolov, V.G.; Volkov, G.A.; Elikin, I.V.; Mysenkov, A.I.

1987-01-01

As is well-known investigations on mathematical models of accidental situations from the point of view of nuclear safety as well as their experimental investigation are of great importance in the design of reactor units for nuclear power plants. This paper gives a review of the state of the art of thermodynamic models and computer codes used for safety analysis of WWER reactors in the USSR, the experimental basis and experimental investigations of the appropriate thermal processes. The actual and future trends of theoretical and experimental investigation on safety problems of WWER type nuclear power plants are briefly described. (author)

Slope-Area Computation Program Graphical User Interface 1.0—A Preprocessing and Postprocessing Tool for Estimating Peak Flood Discharge Using the Slope-Area Method

Science.gov (United States)

Bradley, D. Nathan

2012-01-01

The slope-area method is a technique for estimating the peak discharge of a flood after the water has receded (Dalrymple and Benson, 1967). This type of discharge estimate is called an “indirect measurement” because it relies on evidence left behind by the flood, such as high-water marks (HWMs) on trees or buildings. These indicators of flood stage are combined with measurements of the cross-sectional geometry of the stream, estimates of channel roughness, and a mathematical model that balances the total energy of the flow between cross sections. This is in contrast to a “direct” measurement of discharge during the flood where cross-sectional area is measured and a current meter or acoustic equipment is used to measure the water velocity. When a direct discharge measurement cannot be made at a gage during high flows because of logistics or safety reasons, an indirect measurement of a peak discharge is useful for defining the high-flow section of the stage-discharge relation (rating curve) at the stream gage, resulting in more accurate computation of high flows. The Slope-Area Computation program (SAC; Fulford, 1994) is an implementation of the slope-area method that computes a peak-discharge estimate from inputs of water-surface slope (from surveyed HWMs), channel geometry, and estimated channel roughness. SAC is a command line program written in Fortran that reads input data from a formatted text file and prints results to another formatted text file. Preparing the input file can be time-consuming and prone to errors. This document describes the SAC graphical user interface (GUI), a crossplatform “wrapper” application that prepares the SAC input file, executes the program, and helps the user interpret the output. The SAC GUI is an update and enhancement of the slope-area method (SAM; Hortness, 2004; Berenbrock, 1996), an earlier spreadsheet tool used to aid field personnel in the completion of a slope-area measurement. The SAC GUI reads survey data

Incorporating Traffic Control and Safety Hardware Performance Functions into Risk-based Highway Safety Analysis

Directory of Open Access Journals (Sweden)

Zongzhi Li

2017-04-01

Full Text Available Traffic control and safety hardware such as traffic signs, lighting, signals, pavement markings, guardrails, barriers, and crash cushions form an important and inseparable part of highway infrastructure affecting safety performance. Significant progress has been made in recent decades to develop safety performance functions and crash modification factors for site-specific crash predictions. However, the existing models and methods lack rigorous treatments of safety impacts of time-deteriorating conditions of traffic control and safety hardware. This study introduces a refined method for computing the Safety Index (SI as a means of crash predictions for a highway segment that incorporates traffic control and safety hardware performance functions into the analysis. The proposed method is applied in a computation experiment using five-year data on nearly two hundred rural and urban highway segments. The root-mean square error (RMSE, Chi-square, Spearman’s rank correlation, and Mann-Whitney U tests are employed for validation.

A new modeling approach to the safety evaluation of N-modular redundant computer systems in presence of imperfect maintenance

International Nuclear Information System (INIS)

Flammini, Francesco; Marrone, Stefano; Mazzocca, Nicola; Vittorini, Valeria

2009-01-01

A large number of safety-critical control systems are based on N-modular redundant architectures, using majority voters on the outputs of independent computation units. In order to assess the compliance of these architectures with international safety standards, the frequency of hazardous failures must be analyzed by developing and solving proper formal models. Furthermore, the impact of maintenance faults has to be considered, since imperfect maintenance may degrade the safety integrity level of the system. In this paper, we present both a failure model for voting architectures based on Bayesian networks and a maintenance model based on continuous time Markov chains, and we propose to combine them according to a compositional multiformalism modeling approach in order to analyze the impact of imperfect maintenance on the system safety. We also show how the proposed approach promotes the reuse and the interchange of models as well the interchange of solving tools.

Development of a computer code for low-and intermediate-level radioactive waste disposal safety assessment

International Nuclear Information System (INIS)

Park, J. W.; Kim, C. L.; Lee, E. Y.; Lee, Y. M.; Kang, C. H.; Zhou, W.; Kozak, M. W.

2002-01-01

A safety assessment code, called SAGE (Safety Assessment Groundwater Evaluation), has been developed to describe post-closure radionuclide releases and potential radiological doses for low- and intermediate-level radioactive waste (LILW) disposal in an engineered vault facility in Korea. The conceptual model implemented in the code is focused on the release of radionuclide from a gradually degrading engineered barrier system to an underlying unsaturated zone, thence to a saturated groundwater zone. The radionuclide transport equations are solved by spatially discretizing the disposal system into a series of compartments. Mass transfer between compartments is by diffusion/dispersion and advection. In all compartments, radionuclides are decayed either as a single-member chain or as multi-member chains. The biosphere is represented as a set of steady-state, radionuclide-specific pathway dose conversion factors that are multiplied by the appropriate release rate from the far field for each pathway. The code has the capability to treat input parameters either deterministically or probabilistically. Parameter input is achieved through a user-friendly Graphical User Interface. An application is presented, which is compared against safety assessment results from the other computer codes, to benchmark the reliability of system-level conceptual modeling of the code

Application of personal computer to development of entrance management system for radiating facilities

International Nuclear Information System (INIS)

Suzuki, Shogo; Hirai, Shouji

1989-01-01

The report describes a system for managing the entrance and exit of personnel to radiating facilities. A personal computer is applied to its development. Major features of the system is outlined first. The computer is connected to the gate and two magnetic card readers provided at the gate. The gate, which is installed at the entrance to a room under control, opens only for those who have a valid card. The entrance-exit management program developed is described next. The following three files are used: ID master file (random file of the magnetic card number, name, qualification, etc., of each card carrier), entrance-exit management file (random file of time of entrance/exit, etc., updated everyday), and entrance-exit record file (sequential file of card number, name, date, etc.), which are stored on floppy disks. A display is provided to show various lists including a list of workers currently in the room and a list of workers who left the room at earlier times of the day. This system is useful for entrance management of a relatively small facility. Though small in required cost, it requires only a few operators to perform effective personnel management. (N.K.)

PSAPACK 4.2. A code for probabilistic safety assessment level 1. User's manual

International Nuclear Information System (INIS)

1995-01-01

Only limited use has been made until now of the large amount of information contained in probabilistic safety assessments (PSAs). This is mainly due to the complexity of the PSA reports and the difficulties in obtaining intermediate results and in performing updates and recalculations. Moreover, PSA software was developed for mainframe computers, and the files of information such as fault trees and accident sequences were intended for the use of the analysts carrying out PSA studies or other skilled PSA practitioners. The increasing power and availability of personal computers (PCs) and developments in recent years in both hardware and software have made it possible to develop PSA software for use in PCs. Furthermore, the operational characteristics of PCs make them attractive not only for performing PSAs but also for updating the results and in using them in day-to-day applications. The IAEA has therefore developed in co-operation with its Member States, a software package (PSAPACK) for PCs for use in performing a Level 1 PSA and for easy interrogation of the results. Figs

Design and reliability, availability, maintainability, and safety analysis of a high availability quadruple vital computer system

Institute of Scientific and Technical Information of China (English)

Ping TAN; Wei-ting HE; Jia LIN; Hong-ming ZHAO; Jian CHU

2011-01-01

With the development of high-speed railways in China,more than 2000 high-speed trains will be put into use.Safety and efficiency of railway transportation is increasingly important.We have designed a high availability quadruple vital computer (HAQVC) system based on the analysis of the architecture of the traditional double 2-out-of-2 system and 2-out-of-3 system.The HAQVC system is a system with high availability and safety,with prominent characteristics such as fire-new internal architecture,high efficiency,reliable data interaction mechanism,and operation state change mechanism.The hardware of the vital CPU is based on ARM7 with the real-time embedded safe operation system (ES-OS).The Markov modeling method is designed to evaluate the reliability,availability,maintainability,and safety (RAMS) of the system.In this paper,we demonstrate that the HAQVC system is more reliable than the all voting triple modular redundancy (AVTMR) system and double 2-out-of-2 system.Thus,the design can be used for a specific application system,such as an airplane or high-speed railway system.

How users organize electronic files on their workstations in the office environment: a preliminary study of personal information organization behaviour

Directory of Open Access Journals (Sweden)

Christopher S.G. Khoo

2007-01-01

Full Text Available An ongoing study of how people organize their computer files and folders on the hard disk of their office workstations. A questionnaire was used to collect information on the subjects, their work responsibilities and characteristics of their workstations. Data on file and folder names and file structure were extracted from the hard disk using a computer program STG FolderPrint Plus, DOS command and screen capture. A semi-structured interview collected information on subjects' strategies in naming and organizing files and folders, and in locating and retrieving files. The data were analysed mainly through qualitative analysis and content analysis. The subjects organized their folders in a variety of structures, from broad and shallow to narrow and deep hierarchies. One to three levels of folders is common. The labels for first level folders tended to be task-based or project-based. Most subjects located files by browsing the folder structure, with searching used as a last resort. The most common types of folder names were document type, organizational function or structure, and miscellaneous or temporary. The frequency of folders of different types appear related to the type of occupation.

Defining nuclear medical file formal based on DICOM standard

International Nuclear Information System (INIS)

He Bin; Jin Yongjie; Li Yulan

2001-01-01

With the wide application of computer technology in medical area, DICOM is becoming the standard of digital imaging and communication. The author discusses how to define medical imaging file formal based on DICOM standard. It also introduces the format of ANMIS system the authors defined the validity and integrality of this format

PRO/Mapper: a plotting program for the DEC PRO/300 personal computers utilizing the MAPPER graphics language

International Nuclear Information System (INIS)

Wachter, J.W.

1986-05-01

PRO/Mapper is an application for the Digital Equipment Corporation PRO/300 series of personal computers that facilitates the preparation of visuals such as graphs, charts, and maps in color or black and white. The user prepares an input data file containing English-language commands and writes it into a file using standard editor. PRO/Mapper then reads these files and draws graphs, maps, boxes, and complex line segments onto the computer screen. Axes, curves, and error bars may be plotted in graphical presentations. The commands of PRO/Mapper are a subset of the commands of the more sophisticated MAPPER program written for mainframe computers. The PRO/Mapper commands were chosen primarily for the production of linear graphs. Command files written for the PRO/300 are upward compatible with the Martin Marietta Energy Systems version of MAPPER and can be used to produce publication-quality slides, drawings, and maps on the various output devices of the Oak Ridge National Laboratory mainframe computers

Thermal reactor safety

International Nuclear Information System (INIS)

1980-06-01

Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport

Thermal reactor safety

Energy Technology Data Exchange (ETDEWEB)

1980-06-01

Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

Renewal-anomalous-heterogeneous files

International Nuclear Information System (INIS)

Flomenbom, Ophir

2010-01-01

Renewal-anomalous-heterogeneous files are solved. A simple file is made of Brownian hard spheres that diffuse stochastically in an effective 1D channel. Generally, Brownian files are heterogeneous: the spheres' diffusion coefficients are distributed and the initial spheres' density is non-uniform. In renewal-anomalous files, the distribution of waiting times for individual jumps is not exponential as in Brownian files, yet obeys: ψ α (t)∼t -1-α , 0 2 >, obeys, 2 >∼ 2 > nrml α , where 2 > nrml is the MSD in the corresponding Brownian file. This scaling is an outcome of an exact relation (derived here) connecting probability density functions of Brownian files and renewal-anomalous files. It is also shown that non-renewal-anomalous files are slower than the corresponding renewal ones.

NASA ARCH- A FILE ARCHIVAL SYSTEM FOR THE DEC VAX

Science.gov (United States)

Scott, P. J.

1994-01-01

The function of the NASA ARCH system is to provide a permanent storage area for files that are infrequently accessed. The NASA ARCH routines were designed to provide a simple mechanism by which users can easily store and retrieve files. The user treats NASA ARCH as the interface to a black box where files are stored. There are only five NASA ARCH user commands, even though NASA ARCH employs standard VMS directives and the VAX BACKUP utility. Special care is taken to provide the security needed to insure file integrity over a period of years. The archived files may exist in any of three storage areas: a temporary buffer, the main buffer, and a magnetic tape library. When the main buffer fills up, it is transferred to permanent magnetic tape storage and deleted from disk. Files may be restored from any of the three storage areas. A single file, multiple files, or entire directories can be stored and retrieved. archived entities hold the same name, extension, version number, and VMS file protection scheme as they had in the user's account prior to archival. NASA ARCH is capable of handling up to 7 directory levels. Wildcards are supported. User commands include TEMPCOPY, DISKCOPY, DELETE, RESTORE, and DIRECTORY. The DIRECTORY command searches a directory of savesets covering all three archival areas, listing matches according to area, date, filename, or other criteria supplied by the user. The system manager commands include 1) ARCHIVE- to transfer the main buffer to duplicate magnetic tapes, 2) REPORTto determine when the main buffer is full enough to archive, 3) INCREMENT- to back up the partially filled main buffer, and 4) FULLBACKUP- to back up the entire main buffer. On-line help files are provided for all NASA ARCH commands. NASA ARCH is written in DEC VAX DCL for interactive execution and has been implemented on a DEC VAX computer operating under VMS 4.X. This program was developed in 1985.

PC Graphic file programing

International Nuclear Information System (INIS)

Yang, Jin Seok

1993-04-01

This book gives description of basic of graphic knowledge and understanding and realization of graphic file form. The first part deals with graphic with graphic data, store of graphic data and compress of data, programing language such as assembling, stack, compile and link of program and practice and debugging. The next part mentions graphic file form such as Mac paint file, GEM/IMG file, PCX file, GIF file, and TIFF file, consideration of hardware like mono screen driver and color screen driver in high speed, basic conception of dithering and conversion of formality.

Standards for digital computers used in non-safety nuclear power plant applications: objectives and limitations

International Nuclear Information System (INIS)

Rorer, D.C.; Long, A.B.

1977-01-01

There are currently a number of efforts to develop standards which would apply to digital computers used in nuclear power plants for functions other than those directly involving plant protection (for example, ANS: 4.3.3 Subworking Group in the U.S., IEC 45A/WGA1 Subcommittee in Europe). The impetus for this activity is discussed and generally attributed to the realization that nonsafety systems computers may affect the assumptions used as the design bases for safety systems, the sizable economic loss which can result from the failure of a critical computer application, and the lingering concern about the misapplication of a still-new technology. At the same time, it is pointed out that these standards may create additional obstacles for the use of this new technology which are not present in the application of more conventional instrumentation and control equipment. Much of the U.S. effort has been directed toward the problem of validation of computer systems in which the potential exists for unplanned interactions between various functions in a multiprogram environment, using common hardware in a time-sharing mode. The goal is to develop procedures for the specification, development implementation, and documentation of testable, modular systems which, in the absence of proven quantitative techniques for assessing software reliability, are felt to provide reasonable assurance that the computer system will function as planned

Experiences on File Systems: Which is the best file system for you?

CERN Document Server

Blomer, J

2015-01-01

The distributed file system landscape is scattered. Besides a plethora of research file systems, there is also a large number of production grade file systems with various strengths and weaknesses. The file system, as an abstraction of permanent storage, is appealing because it provides application portability and integration with legacy and third-party applications, including UNIX utilities. On the other hand, the general and simple file system interface makes it notoriously difficult for a distributed file system to perform well under a variety of different workloads. This contribution provides a taxonomy of commonly used distributed file systems and points out areas of research and development that are particularly important for high-energy physics.

Tools for remote computing in accelerator control

International Nuclear Information System (INIS)

Anderssen, P.S.; Frammery, V.; Wilcke, R.

1990-01-01

In modern accelerator control systems, the intelligence of the equipment is distributed in the geographical and the logical sense. Control processes for a large variety of tasks reside in both the equipment and the control computers. Hence successful operation hinges on the availability and reliability of the communication infrastructure. The computers are interconnected by a communication system and use remote procedure calls and message passing for information exchange. These communication mechanisms need a well-defined convention, i.e. a protocol. They also require flexibility in both the setup and changes to the protocol specification. The network compiler is a tool which provides the programmer with a means of establishing such a protocol for his application. Input to the network compiler is a single interface description file provided by the programmer. This file is written according to a grammar, and completely specifies the interprocess communication interfaces. Passed through the network compiler, the interface description file automatically produces the additional source code needed for the protocol. Hence the programmer does not have to be concerned about the details of the communication calls. Any further additions and modifications are made easy, because all the information about the interface is kept in a single file. (orig.)

Software For Computer-Security Audits

Science.gov (United States)

Arndt, Kate; Lonsford, Emily

1994-01-01

Information relevant to potential breaches of security gathered efficiently. Automated Auditing Tools for VAX/VMS program includes following automated software tools performing noted tasks: Privileged ID Identification, program identifies users and their privileges to circumvent existing computer security measures; Critical File Protection, critical files not properly protected identified; Inactive ID Identification, identifications of users no longer in use found; Password Lifetime Review, maximum lifetimes of passwords of all identifications determined; and Password Length Review, minimum allowed length of passwords of all identifications determined. Written in DEC VAX DCL language.

75 FR 27821 - Privacy Act of 1974; System of Records

Science.gov (United States)

2010-05-18

...-USNCB. The files contain electronic and hard copy records containing identifying particulars about... safety from persons, events, or things; investigative notes; computer printouts; letters; memoranda...: Case files closed as of April 5, 1982 and thereafter are disposed of as follows: The hard copy (paper...

Building the safety case for a hypothetical underground repository in crystalline rock. Final report. Vol. 2. Safety file

International Nuclear Information System (INIS)

Biurrun, E.; Engelmann, H.J.; Jobmann, M.; Lommerzheim, A.; Popp, W.; Frentz, R.R. v.; Wahl, A.

1996-10-01

The study was intended as a desk simulation of the process of preparing a licensing application for a deep repository for spent fuel and high level waste in crystalline rock. After clarifying of organizational aspects of table of contents specifying all aspects in a safety life for license application were considered. The volume II is subdivided in two parts. Part A describes the general information, waste description, site characteristics, disposal facility design, reporitory construction and operation, quality assurance, operational safety, repository closure, organization and financial aspects, and long-term safety assessment. Part B deals with the impact of retrievability. (DG)

Development of a computational database for probabilistic safety assessment of nuclear research reactors