Computing and cognition in future power-plant operations

International Nuclear Information System (INIS)

Kisner, R.A.; Sheridan, T.B.

1983-01-01

The intent of this paper is to speculate on the nature of future interactions between people and computers in the operation of power plants. In particular, the authors offer a taxonomy for examining the differing functions of operators in interacting with the plant and its computers, and the differing functions of the computers in interacting with the plant and its operators

Preparation of plant-specific NDA reference material

International Nuclear Information System (INIS)

Abedin-Zadeh, R.; Beetle, T.; Kuhn, E.; Terrey, D.; Turel, S.; Busca, G.; Guardini, S.

1983-01-01

The importance of having suitable and well characterized non-destructive assay (NDA) reference materials for the verification activities of the safeguards control authorities is stressed. The Euratom Inspectorate and the IAEA have initiated an extensive programme for the procurement and preparation of Joint Euratom/IAEA safeguards NDA reference materials with the active participation of the Ispra Establishment of the Euratom Joint Research Centre. The different type and nature of materials, condition of measurements, and plant characteristics and provisions had to be taken into account for plant-specific NDA reference materials. The preparation of each reference material was planned case by case and specific criteria such as limitations in different facilities, measurement capabilities, conditions, product availability and population variability are being ascertained. A procurement scheme was prepared describing step-by-step procedures detailing responsibilities, measurement conditions, destructive analysis schemes, desired characteristics and methods of data evaluation. This paper describes the principles and procedures carried out for the preparation of a reference MOX pin, low enriched uranium reference rods, low enriched uranium reference drums, reference MTR assemblies, and THTR reference pebbles. The scheme for each characterization technique is presented. (author)

The Northeast Utilities generic plant computer system

International Nuclear Information System (INIS)

Spitzner, K.J.

1980-01-01

A variety of computer manufacturers' equipment monitors plant systems in Northeast Utilities' (NU) nuclear and fossil power plants. The hardware configuration and the application software in each of these systems are essentially one of a kind. Over the next few years these computer systems will be replaced by the NU Generic System, whose prototype is under development now for Millstone III, an 1150 Mwe Pressurized Water Reactor plant being constructed in Waterford, Connecticut. This paper discusses the Millstone III computer system design, concentrating on the special problems inherent in a distributed system configuration such as this. (auth)

Interface between computational fluid dynamics (CFD) and plant analysis computer codes

International Nuclear Information System (INIS)

Coffield, R.D.; Dunckhorst, F.F.; Tomlinson, E.T.; Welch, J.W.

1993-01-01

Computational fluid dynamics (CFD) can provide valuable input to the development of advanced plant analysis computer codes. The types of interfacing discussed in this paper will directly contribute to modeling and accuracy improvements throughout the plant system and should result in significant reduction of design conservatisms that have been applied to such analyses in the past

Preparation of plant and system design description documents

International Nuclear Information System (INIS)

1989-01-01

This standard prescribes the purpose, scope, organization, and content of plant design requirements (PDR) documents and system design descriptions (SDDs), to provide a unified approach to their preparation and use by a project as the principal means to establish the plant design requirements and to establish, describe, and control the individual system designs from conception and throughout the lifetime of the plant. The Electric Power Research Institute's Advanced Light Water Reactor (LWR) Requirements Document should be considered for LWR plants

Plant computer system in nuclear power station

International Nuclear Information System (INIS)

Kato, Shinji; Fukuchi, Hiroshi

1991-01-01

In nuclear power stations, centrally concentrated monitoring system has been adopted, and in central control rooms, large quantity of information and operational equipments concentrate, therefore, those become the important place of communication between plants and operators. Further recently, due to the increase of the unit capacity, the strengthening of safety, the problems of man-machine interface and so on, it has become important to concentrate information, to automate machinery and equipment and to simplify them for improving the operational environment, reliability and so on. On the relation of nuclear power stations and computer system, to which attention has been paid recently as the man-machine interface, the example in Tsuruga Power Station, Japan Atomic Power Co. is shown. No.2 plant in the Tsuruga Power Station is a PWR plant with 1160 MWe output, which is a home built standardized plant, accordingly the computer system adopted here is explained. The fundamental concept of the central control board, the process computer system, the design policy, basic system configuration, reliability and maintenance, CRT display, and the computer system for No.1 BWR 357 MW plant are reported. (K.I.)

Computer-based control systems of nuclear power plants

International Nuclear Information System (INIS)

Kalashnikov, V.K.; Shugam, R.A.; Ol'shevsky, Yu.N.

1975-01-01

Computer-based control systems of nuclear power plants may be classified into those using computers for data acquisition only, those using computers for data acquisition and data processing, and those using computers for process control. In the present paper a brief review is given of the functions the systems above mentioned perform, their applications in different nuclear power plants, and some of their characteristics. The trend towards hierarchic systems using control computers with reserves already becomes clear when consideration is made of the control systems applied in the Canadian nuclear power plants that pertain to the first ones equipped with process computers. The control system being now under development for the large Soviet reactors of WWER type will also be based on the use of control computers. That part of the system concerned with controlling the reactor assembly is described in detail

Preparation of environmental reports and impact statements for nuclear power plants

International Nuclear Information System (INIS)

Tsai, Y.H.

1986-01-01

Considerable first-hand experience has accumulated during the past decade in the United States regarding the preparation of environmental reports (ER) and environmental impact statements (EIS) for nuclear power plants. The US Nuclear Regulatory Commission (USNRC), which is responsible for regulating the construction and operation of nuclear power plants, is required under the National Environmental Policy Act to prepare an EIS for each plant. To obtain information essential to the EIS, the USNRC requires that each power company submit an ER. This paper focuses on the interrelationships of the two environmental documents and discusses the environmental review process and the environmental laws and regulations related to the licensing of nuclear power plants. It also describes the format and content, environmental issues, data requirements, and impact assessment methodologies for preparation of the ER and EIS. Problems associated with preparing the EIS are presented, with particular emphasis on the problems and methodologies associated with evaluating environmental costs and benefits

Proceedings: Distributed digital systems, plant process computers, and networks

International Nuclear Information System (INIS)

1995-03-01

These are the proceedings of a workshop on Distributed Digital Systems, Plant Process Computers, and Networks held in Charlotte, North Carolina on August 16--18, 1994. The purpose of the workshop was to provide a forum for technology transfer, technical information exchange, and education. The workshop was attended by more than 100 representatives of electric utilities, equipment manufacturers, engineering service organizations, and government agencies. The workshop consisted of three days of presentations, exhibitions, a panel discussion and attendee interactions. Original plant process computers at the nuclear power plants are becoming obsolete resulting in increasing difficulties in their effectiveness to support plant operations and maintenance. Some utilities have already replaced their plant process computers by more powerful modern computers while many other utilities intend to replace their aging plant process computers in the future. Information on recent and planned implementations are presented. Choosing an appropriate communications and computing network architecture facilitates integrating new systems and provides functional modularity for both hardware and software. Control room improvements such as CRT-based distributed monitoring and control, as well as digital decision and diagnostic aids, can improve plant operations. Commercially available digital products connected to the plant communications system are now readily available to provide distributed processing where needed. Plant operations, maintenance activities, and engineering analyses can be supported in a cost-effective manner. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

Preparation and testing of plant seed meal-based wood adhesives.

Science.gov (United States)

He, Zhongqi; Chapital, Dorselyn C

2015-03-05

Recently, the interest in plant seed meal-based products as wood adhesives has steadily increased, as these plant raw materials are considered renewable and environment-friendly. These natural products may serve as alternatives to petroleum-based adhesives to ease environmental and sustainability concerns. This work demonstrates the preparation and testing of the plant seed-based wood adhesives using cottonseed and soy meal as raw materials. In addition to untreated meals, water washed meals and protein isolates are prepared and tested. Adhesive slurries are prepared by mixing a freeze-dried meal product with deionized water (3:25 w/w) for 2 hr. Each adhesive preparation is applied to one end of 2 wood veneer strips using a brush. The tacky adhesive coated areas of the wood veneer strips are lapped and glued by hot-pressing. Adhesive strength is reported as the shear strength of the bonded wood specimen at break. Water resistance of the adhesives is measured by the change in shear strength of the bonded wood specimens at break after water soaking. This protocol allows one to assess plant seed-based agricultural products as suitable candidates for substitution of synthetic-based wood adhesives. Adjustments to the adhesive formulation with or without additives and bonding conditions could optimize their adhesive properties for various practical applications.

Improved sample preparation for CE-LIF analysis of plant N-glycans.

Science.gov (United States)

Nagels, Bieke; Santens, Francis; Weterings, Koen; Van Damme, Els J M; Callewaert, Nico

2011-12-01

In view of glycomics studies in plants, it is important to have sensitive tools that allow one to analyze and characterize the N-glycans present on plant proteins in different species. Earlier methods combined plant-based sample preparations with CE-LIF N-glycan analysis but suffered from background contaminations, often resulting in non-reproducible results. This publication describes a reproducible and sensitive protocol for the preparation and analysis of plant N-glycans, based on a combination of the 'in-gel release method' and N-glycan analysis on a multicapillary DNA sequencer. Our protocol makes it possible to analyze plant N-glycans starting from low amounts of plant material with highly reproducible results. The developed protocol was validated for different plant species and plant cells. Copyright © 2011 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Computer-assisted power plant management

International Nuclear Information System (INIS)

Boettcher, D.

1990-01-01

Operating a power plant and keeping it operational is ensured by a multiplicity of technical management subtasks which are cross referenced and based on an extensive inventory of descriptive and operational plant data. These data stocks are still registered in an isolated mode and managed and updated manually. This is a labor intensive, error prone procedure. In this situation, the introduction of a computer-assisted plant management system, whose core is a data-base of assured quality common to all activities, and which contains standardized processing aids fully planned for the subtasks occurring in the plant, is likely to achieve a considerable improvement in the quality of plant management and to relieve the staff of administrative activities. (orig.) [de

Computer system for nuclear power plant parameter display

International Nuclear Information System (INIS)

Stritar, A.; Klobuchar, M.

1990-01-01

The computer system for efficient, cheap and simple presentation of data on the screen of the personal computer is described. The display is in alphanumerical or graphical form. The system can be used for the man-machine interface in the process monitoring system of the nuclear power plant. It represents the third level of the new process computer system of the Nuclear Power Plant Krsko. (author)

[Microfungicid--a preparation based on trichoderma viride for plant diseases control].

Science.gov (United States)

Kolombet, L V; Zhigletsova, S K; Derbyshev, V V; Ezhov, D V; Kosareva, N I; Bystrova, E V

2001-01-01

A technology was designed for manufacturing a preparation based on Trichoderma viride Pers ex S.F. Gray that strongly suppresses the development of causative agents of certain plant diseases and displays a growth-stimulating activity. Cultivation of the strain in a liquid medium for 18-24 h produced up to 60 g dry biomass per liter nutrient medium. A marketable form created in this work conserves the activity of the mycelial preparation for six months. The preparation is compatible with insecticides (carbofos, vismetrin, talstar, and applaud) and certain fungicides (such as baitan). Tests performed with the liquid form of Mycofungicid (seeds were treated with this preparation at a dose of 20-30 g per metric ton before sowing) showed its high efficiency in protecting cereal crops from plant pathogens. The incidence of plant diseases decreased by 65%, and crop yields increased by 15-20%.

Guidelines for preparing specifications for nuclear power plants (NCIG-04): Final report

International Nuclear Information System (INIS)

1988-04-01

This document provides guidance for preparing technical requirements used in procurement and installation specifications. It is a compilation of recommend practices for writing specifications to preserve the best guidance coming out of recent years experience from construction of nuclear plants. It is intended to: Establish good practices for the content of specifications used for nuclear power plants; Be applicable to a wide range of specifications used for initial construction of plants and modifications to existing plants, including equipment replacement; and Provide guidance to specification preparers and reviewers

REAL TIME PULVERISED COAL FLOW SOFT SENSOR FOR THERMAL POWER PLANTS USING EVOLUTIONARY COMPUTATION TECHNIQUES

Directory of Open Access Journals (Sweden)

B. Raja Singh

2015-01-01

Full Text Available Pulverised coal preparation system (Coal mills is the heart of coal-fired power plants. The complex nature of a milling process, together with the complex interactions between coal quality and mill conditions, would lead to immense difficulties for obtaining an effective mathematical model of the milling process. In this paper, vertical spindle coal mills (bowl mill that are widely used in coal-fired power plants, is considered for the model development and its pulverised fuel flow rate is computed using the model. For the steady state coal mill model development, plant measurements such as air-flow rate, differential pressure across mill etc., are considered as inputs/outputs. The mathematical model is derived from analysis of energy, heat and mass balances. An Evolutionary computation technique is adopted to identify the unknown model parameters using on-line plant data. Validation results indicate that this model is accurate enough to represent the whole process of steady state coal mill dynamics. This coal mill model is being implemented on-line in a 210 MW thermal power plant and the results obtained are compared with plant data. The model is found accurate and robust that will work better in power plants for system monitoring. Therefore, the model can be used for online monitoring, fault detection, and control to improve the efficiency of combustion.

Cone-beam computed tomography analysis of curved root canals after mechanical preparation with three nickel-titanium rotary instruments

Science.gov (United States)

Elsherief, Samia M.; Zayet, Mohamed K.; Hamouda, Ibrahim M.

2013-01-01

Cone beam computed tomography is a 3-dimensional high resolution imaging method. The purpose of this study was to compare the effects of 3 different NiTi rotary instruments used to prepare curved root canals on the final shape of the curved canals and total amount of root canal transportation by using cone-beam computed tomography. A total of 81 mesial root canals from 42 extracted human mandibular molars, with a curvature ranging from 15 to 45 degrees, were selected. Canals were randomly divided into 3 groups of 27 each. After preparation with Protaper, Revo-S and Hero Shaper, the amount of transportation and centering ability that occurred were assessed by using cone beam computed tomography. Utilizing pre- and post-instrumentation radiographs, straightening of the canal curvatures was determined with a computer image analysis program. Canals were metrically assessed for changes (surface area, changes in curvature and transportation) during canal preparation by using software SimPlant; instrument failures were also recorded. Mean total widths and outer and inner width measurements were determined on each central canal path and differences were statistically analyzed. The results showed that all instruments maintained the original canal curvature well with no significant differences between the different files (P = 0.226). During preparation there was failure of only one file (the protaper group). In conclusion, under the conditions of this study, all instruments maintained the original canal curvature well and were safe to use. Areas of uninstrumented root canal wall were left in all regions using the various systems. PMID:23885273

HTTR plant dynamic simulation using a hybrid computer

International Nuclear Information System (INIS)

Shimazaki, Junya; Suzuki, Katsuo; Nabeshima, Kunihiko; Watanabe, Koichi; Shinohara, Yoshikuni; Nakagawa, Shigeaki.

1990-01-01

A plant dynamic simulation of High-Temperature Engineering Test Reactor has been made using a new-type hybrid computer. This report describes a dynamic simulation model of HTTR, a hybrid simulation method for SIMSTAR and some results obtained from dynamics analysis of HTTR simulation. It concludes that the hybrid plant simulation is useful for on-line simulation on account of its capability of computation at high speed, compared with that of all digital computer simulation. With sufficient accuracy, 40 times faster computation than real time was reached only by changing an analog time scale for HTTR simulation. (author)

Trend of computer-based console for nuclear power plants

International Nuclear Information System (INIS)

Wajima, Tsunetaka; Serizawa, Michiya

1975-01-01

The amount of informations to be watched by the operators in the central operation room increased with the increase of the capacity of nuclear power generation plants, and the necessity of computer-based consoles, in which the informations are compiled and the rationalization of the interface between the operators and the plants is intended by introducing CRT displays and process computers, became to be recognized. The integrated monitoring and controlling system is explained briefly by taking Dungeness B Nuclear Power Station in Britain as a typical example. This power station comprises two AGRs, and these two plants can be controlled in one central control room, each by one man. Three computers including stand-by one are installed. Each computer has the core memory of 16 K words (24 bits/word), and 4 magnetic drums of 256 K words are installed as the external memory. The peripheral equipments are 12 CRT displays, 6 typewriters, high speed tape reader and tape punch for each plant. The display and record of plant data, the analysis, display and record of alarms, the control of plants including reactors, and post incident record are assigned to the computers. In Hitachi Ltd. in Japan, the introduction of color CRTs, the developments of operating consoles, new data-accessing method, and the consoles for maintenance management are in progress. (Kako, I.)

Virtual fragment preparation for computational fragment-based drug design.

Science.gov (United States)

Ludington, Jennifer L

2015-01-01

Fragment-based drug design (FBDD) has become an important component of the drug discovery process. The use of fragments can accelerate both the search for a hit molecule and the development of that hit into a lead molecule for clinical testing. In addition to experimental methodologies for FBDD such as NMR and X-ray Crystallography screens, computational techniques are playing an increasingly important role. The success of the computational simulations is due in large part to how the database of virtual fragments is prepared. In order to prepare the fragments appropriately it is necessary to understand how FBDD differs from other approaches and the issues inherent in building up molecules from smaller fragment pieces. The ultimate goal of these calculations is to link two or more simulated fragments into a molecule that has an experimental binding affinity consistent with the additive predicted binding affinities of the virtual fragments. Computationally predicting binding affinities is a complex process, with many opportunities for introducing error. Therefore, care should be taken with the fragment preparation procedure to avoid introducing additional inaccuracies.This chapter is focused on the preparation process used to create a virtual fragment database. Several key issues of fragment preparation which affect the accuracy of binding affinity predictions are discussed. The first issue is the selection of the two-dimensional atomic structure of the virtual fragment. Although the particular usage of the fragment can affect this choice (i.e., whether the fragment will be used for calibration, binding site characterization, hit identification, or lead optimization), general factors such as synthetic accessibility, size, and flexibility are major considerations in selecting the 2D structure. Other aspects of preparing the virtual fragments for simulation are the generation of three-dimensional conformations and the assignment of the associated atomic point charges.

Recent computer applications in boiling water reactor power plants

International Nuclear Information System (INIS)

Hiraga, Shoji; Joge, Toshio; Kiyokawa, Kazuhiro; Kato, Kanji; Nigawara, Seiitsu

1976-01-01

Process computers in boiling water reactor power plants have won the position of important equipments for the calculation of the core and plant performances and for data logging. Their application technique is growing larger and larger every year. Here, two systems are introduced; plant diagnostic system and computerized control panel. The plant diagnostic system consists of the part processing the signals from a plant, the operation part mainly composed of a computer to diagnose the operating conditions of each system component using input signal, and the result display (CRT or typewriter). The concept on the indications on control panels in nuclear power plants is changing from ''Plant parameters and to be indicated on panel meters as much as possible'' to ''Only the data required for operation are to be indicated.'' Thus the computerized control panel is attracting attention, in which the process computer for processing the operating information and CRT display are introduced. The experimental model of that panel comprises and operator's console and a chief watchmen's console. Its functions are dialogic data access and the automatic selection of preferential information. (Wakatsuki, Y.)

Plant process computer replacements - techniques to limit installation schedules and costs

International Nuclear Information System (INIS)

Baker, M.D.; Olson, J.L.

1992-01-01

Plant process computer systems, a standard fixture in all nuclear power plants, are used to monitor and display important plant process parameters. Scanning thousands of field sensors and alarming out-of-limit values, these computer systems are heavily relied on by control room operators. The original nuclear steam supply system (NSSS) vendor for the power plant often supplied the plant process computer. Designed using sixties and seventies technology, a plant's original process computer has been obsolete for some time. Driven by increased maintenance costs and new US Nuclear Regulatory Commission regulations such as NUREG-0737, Suppl. 1, many utilities have replaced their process computers with more modern computer systems. Given that computer systems are by their nature prone to rapid obsolescence, this replacement cycle will likely repeat. A process computer replacement project can be a significant capital expenditure and must be performed during a scheduled refueling outage. The object of the installation process is to install a working system on schedule. Experience gained by supervising several computer replacement installations has taught lessons that, if applied, will shorten the schedule and limit the risk of costly delays. Examples illustrating this technique are given. This paper and these examples deal only with the installation process and assume that the replacement computer system has been adequately designed, and development and factory tested

Modernization of computer of plant Vandellos-II

International Nuclear Information System (INIS)

Fuente Arias, E. de la

2014-01-01

The Plant computer from the nuclear de Vandellos II, whose modernization process will carry out Westinghouse, is a centralized system which performs monitoring and supervision in real time of plant processes and which performs the calculations necessary for an efficient assessment of plant operation, without performing any action on it. Its main function is to provide current and historical information on the status of the plant, both in normal operation and emergency conditions. (Author)

Two mini-preparation protocols to DNA extraction from plants with ...

African Journals Online (AJOL)

Were standardized two previously reported standard plant DNA extraction methods, but improved them on mini preparations to use the samples for population genetic analysis. The combination of CTAB lysis procedure-solvent extraction and DNA column purification (DNeasy plant mini kit modification) enables a faster and ...

Computer aids for plant operators

International Nuclear Information System (INIS)

Joly, J.P.

1992-01-01

For some time, particularly since the TMI accident, nuclear power plant operators have been aware of the difficulties involved in diagnosing accidents and returning plants to their stable, safe operating mode. There are various possible solutions to these problems: improve control organization during accident situations, rewrite control procedures, integrate safety engineers in shifts, improve control rooms, and implement additional computer aids. The purpose of this presentation is to describe the efforts undertaken by EDF over the last few years in this field

Reviewing computer capabilities in nuclear power plants

International Nuclear Information System (INIS)

1990-06-01

The OSART programme of the IAEA has become an effective vehicle for promoting international co-operation for the enhancement of plant operational safety. In order to maintain consistency in the OSART reviews, OSART Guidelines have been developed which are intended to ensure that the reviewing process is comprehensive. Computer technology is an area in which rapid development is taking place and new applications may be computerized to further enhance safety and the effectiveness of the plant. Supplementary guidance and reference material is needed to help attain comprehensiveness and consistency in OSART reviews. This document is devoted to the utilization of on-site and off-site computers in such a way that the safe operation of the plant is supported. In addition to the main text, there are several annexes illustrating adequate practices as found at various operating nuclear power plants. Refs, figs and tabs

Preparation of labelled lipids by the use of plant cell cultures

International Nuclear Information System (INIS)

Mangold, H.K.

1978-01-01

The preparation of some radioacitvely labelled lipids by the use of plant cell cultures is discussed and further applications of the new method are suggested. Cell suspension cultures of rape (Brassica napus) and soya (Glycine max) have been used for the preparation of lipids labelled with radioisotopes. Radioactive acetic acid as well as various long-chain fatty acids are readily incorporated into the neutral and ionic lipids of plant cell cultures. In addition, 14 C-labelled glycerol, ethanolamine and choline are well utilized by the cells. Randomly labelled lipids have been obtained by incubating cell suspension cultures of rape and soya with [1- 14 C] acetic acid, and uniformly labelled lipids have been isolated from cultures that had been incubated with a mixture of [1- 14 C] acetic acid plus [2- 14 C] acetic acid. The use of techniques of plant cell cultures for the preparation of lipds labelled with stable or radioactive isotopesappears particularly rewarding because the uptake of precursors by the cells and their incorporation into various lipid compounds proceeds rapidly and often quanitatively.This new approach should be useful also for the biosynthesis of lipids whose acyl moieties contain a spn radical, a fluorescent group, or a light-sensitive label. Thus, plant cell cultures constitute valuable new tools for the biosynthetic preparation of a great variety of labelled lipids. (A.G.)

Proceedings of national symposium on computer applications in power plants

International Nuclear Information System (INIS)

1992-01-01

The National Symposium on Computer Applications in Power Plants was organized to help promote exchange of views among scientists and engineers engaged in design, engineering, operation and maintenance of computer based systems in nuclear power plants, conventional power plants, heavy water plants, nuclear fuel cycle facilities and allied industries. About one hundred papers were presented at the Symposium. Those falling within the subject scope of INIS have been processed separately. (author)

Innovative plant protection means prepared natural raw materials

Directory of Open Access Journals (Sweden)

Omar Lomtadze

2018-03-01

Full Text Available Were developed new compositions preparation against pests and diseases of plant: Insekto-acaricide “Antipest”, Fungicide “Antifungal”, a drug against of overwintering pests “Proinsekt” and nutritious preparation “Si-humate”.The effectiveness of trial oil-emulsion preparation “Proinsect” was assessed by the spread of pests - San Jose scale (Diaspidiotus perniciosus and mountain ash bentwing (Leucoptera scitella Costa on treated trees. According to field testing, the efficiency of preparation “Proinsect” exceeds the effectiveness of one of the best imported oily preparation “Sipcomol”, which was selected as a reference.Joint content in composition of synthetic pyretroids with turpentine oil, supposedly synergism takes place (turpentines cause prolonged action of synthetic pyrethroid. In working solutions, obtained from turpentine oil containing composition concentration of pyretroid is low, but it is enough during the whole period of pest development cycle. According to the comparative field testing of “Antipest” and imported preparations, against for fruits pests their efficiency is at almost one level, despite the low content (by 30–40% of pyrethroid (cypermethrin in “Antipest”.The developed phosphate preparation “Antifungal” is a little bit less effective compared to Bordeaux mixture. If well take into account significant decrease of intensity of disease spread and development after the action of phosphate preparation, also very low toxicity zinc hydro- and dihydrophosphates compared to the blue vitriol (Copper(II sulfate, the developed fungicide preparation can be successfully used instead of traditional Bordeaux mixture and in particular against the peach leaf curl.According to the results of field trials, effect, of developed silicon containing humic nutrient composition -“Si-humate” on experimental 2-year-old seedlings apples and peach is on the average 15–17% better than the control ones in

The Stability of Medicinal Plant microRNAs in the Herb Preparation Process.

Science.gov (United States)

Xie, Wenyan; Melzig, Matthias F

2018-04-16

Herbal medicine is now globally accepted as a valid alternative system of pharmaceutical therapies. Various studies around the world have been initiated to develop scientific evidence-based herbal therapies. Recently, the therapeutic potential of medicinal plant derived miRNAs has attracted great attraction. MicroRNAs have been indicated as new bioactive ingredients in medicinal plants. However, the stability of miRNAs during the herbal preparation process and their bioavailability in humans remain unclear. Viscum album L. (European mistletoe) has been widely used in folk medicine for the treatment of cancer and cardiovascular diseases. Our previous study has indicated the therapeutic potential of mistletoe miRNAs by using bioinformatics tools. To evaluate the stability of these miRNAs, various mistletoe extracts that mimic the clinical medicinal use as well as traditional folk medicinal use were prepared. The mistletoe miRNAs including miR166a-3p, miR159a, miR831-5p, val-miR218 and val-miR11 were quantified by stem-loop qRT-PCR. As a result, miRNAs were detectable in the majority of the extracts, indicating that consumption of medicinal plant preparations might introduce miRNAs into mammals. The factors that might cause miRNA degradation include ultrasonic treatment, extreme heat, especially RNase treatment, while to be associated with plant molecules (e.g., proteins, exosomes) might be an efficient way to protect miRNAs against degradation. Our study confirmed the stability of plant derived miRNAs during herb preparations, suggesting the possibility of functionally intact medicinal plant miRNAs in mammals.

The Plant-Window System: A framework for an integrated computing environment at advanced nuclear power plants

International Nuclear Information System (INIS)

Wood, R.T.; Mullens, J.A.; Naser, J.A.

1997-01-01

Power plant data, and the information that can be derived from it, provide the link to the plant through which the operations, maintenance and engineering staff understand and manage plant performance. The extensive use of computer technology in advanced reactor designs provides the opportunity to greatly expand the capability to obtain, analyze, and present data about the plant to station personnel. However, to support highly efficient and increasingly safe operation of nuclear power plants, it is necessary to transform the vast quantity of available data into clear, concise, and coherent information that can be readily accessed and used throughout the plant. This need can be met by an integrated computer workstation environment that provides the necessary information and software applications, in a manner that can be easily understood and sued, to the proper users throughout the plan. As part of a Cooperative Research and Development Agreement with the Electric Power Research Institute, the Oak Ridge National laboratory has developed functional requirements for a Plant-Wide Integrated Environment Distributed On Workstations (Plant-Window) System. The Plant-Window System (PWS) can serve the needs of operations, engineering, and maintenance personnel at nuclear power stations by providing integrated data and software applications within a common computing environment. The PWS requirements identify functional capabilities and provide guidelines for standardized hardware, software, and display interfaces so as to define a flexible computing environment for both current generation nuclear power plants and advanced reactor designs

Cloud Computing with iPlant Atmosphere.

Science.gov (United States)

McKay, Sheldon J; Skidmore, Edwin J; LaRose, Christopher J; Mercer, Andre W; Noutsos, Christos

2013-10-15

Cloud Computing refers to distributed computing platforms that use virtualization software to provide easy access to physical computing infrastructure and data storage, typically administered through a Web interface. Cloud-based computing provides access to powerful servers, with specific software and virtual hardware configurations, while eliminating the initial capital cost of expensive computers and reducing the ongoing operating costs of system administration, maintenance contracts, power consumption, and cooling. This eliminates a significant barrier to entry into bioinformatics and high-performance computing for many researchers. This is especially true of free or modestly priced cloud computing services. The iPlant Collaborative offers a free cloud computing service, Atmosphere, which allows users to easily create and use instances on virtual servers preconfigured for their analytical needs. Atmosphere is a self-service, on-demand platform for scientific computing. This unit demonstrates how to set up, access and use cloud computing in Atmosphere. Copyright © 2013 John Wiley & Sons, Inc.

A guidance on MELCOR input preparation : An input deck for Ul-Chin 3 and 4 Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Cho, Song Won

1997-02-01

The objective of this study is to enhance the capability of assessing the severe accident sequence analyses and the containment behavior using MELCOR computer code and to provide the guideline of its efficient use. This report shows the method of the input deck preparation as well as the assessment strategy for the MELCOR code. MELCOR code is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. The code is being developed at Sandia National Laboratories for the U.S. NRC as a second generation plant risk assessment tool and the successor to the source term code package. The accident sequence of the reference input deck prepared in this study for Ulchin unit 3 and 4 nuclear power plants, is the total loss of feedwater (TLOFW) without any success of safety systems, which is similar to station blackout (TLMB). It is very useful to simulate a well-known sequence through the best estimated code or experiment, because the results of the simulation before core melt can be compared with the FSAR, but no data is available after core melt. The precalculation for the TLOFW using the reference input deck is performed successfully as expected. The other sequences will be carried out with minor changes in the reference input. This input deck will be improved continually by the adding of the safety systems not included in this input deck, and also through the sensitivity and uncertainty analyses. (author). 19 refs., 10 tabs., 55 figs.

A guidance on MELCOR input preparation : An input deck for Ul-Chin 3 and 4 Nuclear Power Plant

International Nuclear Information System (INIS)

Cho, Song Won.

1997-02-01

The objective of this study is to enhance the capability of assessing the severe accident sequence analyses and the containment behavior using MELCOR computer code and to provide the guideline of its efficient use. This report shows the method of the input deck preparation as well as the assessment strategy for the MELCOR code. MELCOR code is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. The code is being developed at Sandia National Laboratories for the U.S. NRC as a second generation plant risk assessment tool and the successor to the source term code package. The accident sequence of the reference input deck prepared in this study for Ulchin unit 3 and 4 nuclear power plants, is the total loss of feedwater (TLOFW) without any success of safety systems, which is similar to station blackout (TLMB). It is very useful to simulate a well-known sequence through the best estimated code or experiment, because the results of the simulation before core melt can be compared with the FSAR, but no data is available after core melt. The precalculation for the TLOFW using the reference input deck is performed successfully as expected. The other sequences will be carried out with minor changes in the reference input. This input deck will be improved continually by the adding of the safety systems not included in this input deck, and also through the sensitivity and uncertainty analyses. (author). 19 refs., 10 tabs., 55 figs

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)

Adverse effects of plant food supplements and botanical preparations

DEFF Research Database (Denmark)

Di Lorenzo, Chiara; Ceschi, Alessandro; Kupferschmidt, Hugo

2015-01-01

The objective of this review was to collect available data on the following: (i) adverse effects observed in humans from the intake of plant food supplements or botanical preparations; (ii) the misidentification of poisonous plants; and (iii) interactions between plant food supplements...... evaluated according to the World Health Organization Guidelines for causality assessment. Data were obtained for 66 plants that are common ingredients of plant food supplements; of the 492 papers selected, 402 (81.7%) dealt with adverse effects directly associated with the botanical and 89 (18.1%) concerned......) the number of severe clinical reactions was very limited, but some fatal cases have been described. Data presented in this review were assessed for quality in order to make the results maximally useful for clinicians in identifying or excluding deleterious effects of botanicals....

The Stability of Medicinal Plant microRNAs in the Herb Preparation Process

Directory of Open Access Journals (Sweden)

Wenyan Xie

2018-04-01

Full Text Available Herbal medicine is now globally accepted as a valid alternative system of pharmaceutical therapies. Various studies around the world have been initiated to develop scientific evidence-based herbal therapies. Recently, the therapeutic potential of medicinal plant derived miRNAs has attracted great attraction. MicroRNAs have been indicated as new bioactive ingredients in medicinal plants. However, the stability of miRNAs during the herbal preparation process and their bioavailability in humans remain unclear. Viscum album L. (European mistletoe has been widely used in folk medicine for the treatment of cancer and cardiovascular diseases. Our previous study has indicated the therapeutic potential of mistletoe miRNAs by using bioinformatics tools. To evaluate the stability of these miRNAs, various mistletoe extracts that mimic the clinical medicinal use as well as traditional folk medicinal use were prepared. The mistletoe miRNAs including miR166a-3p, miR159a, miR831-5p, val-miR218 and val-miR11 were quantified by stem-loop qRT-PCR. As a result, miRNAs were detectable in the majority of the extracts, indicating that consumption of medicinal plant preparations might introduce miRNAs into mammals. The factors that might cause miRNA degradation include ultrasonic treatment, extreme heat, especially RNase treatment, while to be associated with plant molecules (e.g., proteins, exosomes might be an efficient way to protect miRNAs against degradation. Our study confirmed the stability of plant derived miRNAs during herb preparations, suggesting the possibility of functionally intact medicinal plant miRNAs in mammals.

Computer Security: Protect your plant: a "serious game" about control system cyber-security

CERN Multimedia

Stefan Lueders, Computer Security Team

2015-01-01

Control system cyber-security is attracting increasing attention: from cybercriminals, from the media and from security researchers.   After the legendary “Stuxnet” attacks of 2010 against an Iranian uranium enrichment plant, the infiltration of Saudi Aramco in 2012, and most recently the hacking of German blast furnaces, we should be prepared. Just imagine what would happen if hackers turned off the lights in Geneva and the Pays-de-Gex for a month? (“Hacking control systems, switching lights off!"). Or if attackers infiltrated CERN’s accelerator or experiment control systems and stopped us from pursuing our core business: delivering beams and recording particle collisions (“Hacking control systems, switching... accelerators off?"). Now you can test your ability to protect an industrial plant against cyber-threats! The Computer Security Team, in collaboration with Kaspersky Lab, is organising a so-...

Rapid immunohistochemical diagnosis of tobacco mosaic virus disease by microwave-assisted plant sample preparation

Science.gov (United States)

Zellnig, Günther; Möstl, Stefan; Zechmann, Bernd

2013-01-01

Immunoelectron microscopy is a powerful method to diagnose viral diseases and to study the distribution of the viral agent within plant cells and tissues. Nevertheless, current protocols for the immunological detection of viral diseases with transmission electron microscopy (TEM) in plants take between 3 and 6 days and are therefore not suited for rapid diagnosis of virus diseases in plants. In this study, we describe a method that allows rapid cytohistochemical detection of tobacco mosaic virus (TMV) in leaves of tobacco plants. With the help of microwave irradiation, sample preparation of the leaves was reduced to 90 min. After sample sectioning, virus particles were stained on the sections by immunogold labelling of the viral coat protein, which took 100 min. After investigation with the TEM, a clear visualization of TMV in tobacco cells was achieved altogether in about half a day. Comparison of gold particle density by image analysis revealed that samples prepared with the help of microwave irradiation yielded significantly higher gold particle density as samples prepared conventionally at room temperature. This study clearly demonstrates that microwave-assisted plant sample preparation in combination with cytohistochemical localization of viral coat protein is well suited for rapid diagnosis of plant virus diseases in altogether about half a day by TEM. PMID:23580761

Quality control of repair of equipment for coal preparation plants. Upravlenie kachestvom remonta oborudovaniya ugleobogatitel'nykh fabrik

Energy Technology Data Exchange (ETDEWEB)

Okonishnikov, A I; Neskoromnykh, V M; Surzhenko, V S; Sirichenko, R P; Pavlyuchenko, S G; Lesikov, A V

1984-01-01

The Ukrniiugleobogashchenie, Kalininsk and Sukhodol'sk coal preparation plants have developed the SUKRO system for control of repair quality of coal preparation equipment in the USSR. The system is based on a system of standards used in coal preparation plants. The following systems of standards used by the SUKRO system are analyzed: organization standards (order of repair in a coal preparation plant, repair planning, spare part systems, methods for determining equipment wear, analysis of equipment failures), standards for maintenance and repair (methods for equipment maintenance, service life of each equipment component or system, structure of preventive repair or repair, organizational models of repair operations, lubrication systems), standards for assessment of labor quality during repair operations. Use of the SUKRO system in the Sukhodol'sk coal preparation plant is evaluated. The SUKRO forms a system of standards for repair and maintenance of equipment considering operation conditions in coal preparation plants, requirements for equipment reliability and service life. (4 refs.)

Application of statistical method for FBR plant transient computation

International Nuclear Information System (INIS)

Kikuchi, Norihiro; Mochizuki, Hiroyasu

2014-01-01

Highlights: • A statistical method with a large trial number up to 10,000 is applied to the plant system analysis. • A turbine trip test conducted at the “Monju” reactor is selected as a plant transient. • A reduction method of trial numbers is discussed. • The result with reduced trial number can express the base regions of the computed distribution. -- Abstract: It is obvious that design tolerances, errors included in operation, and statistical errors in empirical correlations effect on the transient behavior. The purpose of the present study is to apply above mentioned statistical errors to a plant system computation in order to evaluate the statistical distribution contained in the transient evolution. A selected computation case is the turbine trip test conducted at 40% electric power of the prototype fast reactor “Monju”. All of the heat transport systems of “Monju” are modeled with the NETFLOW++ system code which has been validated using the plant transient tests of the experimental fast reactor Joyo, and “Monju”. The effects of parameters on upper plenum temperature are confirmed by sensitivity analyses, and dominant parameters are chosen. The statistical errors are applied to each computation deck by using a pseudorandom number and the Monte-Carlo method. The dSFMT (Double precision SIMD-oriented Fast Mersenne Twister) that is developed version of Mersenne Twister (MT), is adopted as the pseudorandom number generator. In the present study, uniform random numbers are generated by dSFMT, and these random numbers are transformed to the normal distribution by the Box–Muller method. Ten thousands of different computations are performed at once. In every computation case, the steady calculation is performed for 12,000 s, and transient calculation is performed for 4000 s. In the purpose of the present statistical computation, it is important that the base regions of distribution functions should be calculated precisely. A large number of

Computer-Aided Drug Discovery in Plant Pathology.

Science.gov (United States)

Shanmugam, Gnanendra; Jeon, Junhyun

2017-12-01

Control of plant diseases is largely dependent on use of agrochemicals. However, there are widening gaps between our knowledge on plant diseases gained from genetic/mechanistic studies and rapid translation of the knowledge into target-oriented development of effective agrochemicals. Here we propose that the time is ripe for computer-aided drug discovery/design (CADD) in molecular plant pathology. CADD has played a pivotal role in development of medically important molecules over the last three decades. Now, explosive increase in information on genome sequences and three dimensional structures of biological molecules, in combination with advances in computational and informational technologies, opens up exciting possibilities for application of CADD in discovery and development of agrochemicals. In this review, we outline two categories of the drug discovery strategies: structure- and ligand-based CADD, and relevant computational approaches that are being employed in modern drug discovery. In order to help readers to dive into CADD, we explain concepts of homology modelling, molecular docking, virtual screening, and de novo ligand design in structure-based CADD, and pharmacophore modelling, ligand-based virtual screening, quantitative structure activity relationship modelling and de novo ligand design for ligand-based CADD. We also provide the important resources available to carry out CADD. Finally, we present a case study showing how CADD approach can be implemented in reality for identification of potent chemical compounds against the important plant pathogens, Pseudomonas syringae and Colletotrichum gloeosporioides .

Preparation for and building of V-1 nuclear power plant

International Nuclear Information System (INIS)

Smatlak, S.; Spirko, M.

1981-01-01

Some findings and problems encountered during the construction of the V-1 nuclear power plant at Jaslovske Bohunice are discussed from the point of view of the investor, mainly problems associated with project preparation and relations between suppliers and the customer. The progress of construction is described and the dates are shown of the main stages of construction and tests. The construction proceeded according to a net diagram and was controlled by the construction management and a coordination group headed by the investor. An international start-up commission was established for the start-up stage. The fields are outlined of the participation and co-operation of Soviet organizations during project preparation, supplies, assembly, start-up, and fuel supplies for the V-1 nuclear power plant. (B.S.)

Improvement in water-slurry circulation at the Chumakovskaya coal preparation plant

Energy Technology Data Exchange (ETDEWEB)

Nabokov, A.K.; Fedotov, B.P.; Mitlash, V.V.

1988-02-01

The Chumakovskaya coal preparation plant (Donetskugleobogashchenie association) was put into operation in 1935. It processes 570 t/h of coal slurry with an ash content of 38.6% and produces grade T coal for coking and power generation. Coal preparation technology used is described. Shortcomings of the system cause 130 kg of high ash slurries to be recirculated per m/sup 3/ of hydrocyclone drain. Mathematical analysis of the present process and of two improved variants is presented. The analysis permits variants for clarification of the recirculated water to be developed and evaluated and the best one to be selected. The optimum variant permits the amount of thin recirculated slurry to be reduced to 48% and the amount of granular slurry to 13%. Implementation of this variant at the Chumakovskaya coal preparation plant will ensure annual savings of 20,000 rubles.

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)

Coal Preparation and Processing Plants New Source Performance Standards (NSPS)

Science.gov (United States)

Learn about the NSPS regulation for coal preparation and processing plants by reading the rule summary, the rule history, the code of federal regulation text, the federal register, and additional docket documents

Understanding Plant Nitrogen Metabolism through Metabolomics and Computational Approaches

Directory of Open Access Journals (Sweden)

Perrin H. Beatty

2016-10-01

Full Text Available A comprehensive understanding of plant metabolism could provide a direct mechanism for improving nitrogen use efficiency (NUE in crops. One of the major barriers to achieving this outcome is our poor understanding of the complex metabolic networks, physiological factors, and signaling mechanisms that affect NUE in agricultural settings. However, an exciting collection of computational and experimental approaches has begun to elucidate whole-plant nitrogen usage and provides an avenue for connecting nitrogen-related phenotypes to genes. Herein, we describe how metabolomics, computational models of metabolism, and flux balance analysis have been harnessed to advance our understanding of plant nitrogen metabolism. We introduce a model describing the complex flow of nitrogen through crops in a real-world agricultural setting and describe how experimental metabolomics data, such as isotope labeling rates and analyses of nutrient uptake, can be used to refine these models. In summary, the metabolomics/computational approach offers an exciting mechanism for understanding NUE that may ultimately lead to more effective crop management and engineered plants with higher yields.

Computer simulation of thermal plant operations

CERN Document Server

O'Kelly, Peter

2012-01-01

This book describes thermal plant simulation, that is, dynamic simulation of plants which produce, exchange and otherwise utilize heat as their working medium. Directed at chemical, mechanical and control engineers involved with operations, control and optimization and operator training, the book gives the mathematical formulation and use of simulation models of the equipment and systems typically found in these industries. The author has adopted a fundamental approach to the subject. The initial chapters provide an overview of simulation concepts and describe a suitable computer environment.

Computer-aided preparation of specifications for radial fans at VEB Lufttechnische Anlagen Berlin

Energy Technology Data Exchange (ETDEWEB)

Kubis, R.; Kull, W.

1987-01-01

The specification details the scope of delivery for radial fans on a standard page and also serves the preparation for production. In the place of previous manual preparation, a computer-aided technique for the office computer is presented that provides the technical parameters from data files out of few input data to identify the fan type. The data files and evaluative programs are based on the software tool REDABAS and the SCP operating system. Using this technique it has been possible to cut considerably the preparation time for the incoming orders.

The management plan preparation activities nuclear power plant in Indonesia

International Nuclear Information System (INIS)

Utomo

2011-01-01

A feasibility Study that has been updated show that two nuclear power units with each unit of power up to 1000 MWe can represent decently an economical alternative energy supply. It added that the available time schedule was quite tight so that the preparation for the development must be starting first. This paper will discuss the preparation of plans of the first nuclear power plant which includes program activities, the structure of contracts, schedules of activities and funding. From the information obtained to date that in addition to a candidate site that is ready to be built in Muria peninsula is still required another potential alternative site besides to search other complete data information. This site investigation activities completed within the time schedule was passed ''critical path'', so that these activities should be carried out intensively and obey the time. This paper describes the steps that need to be prepared to welcome the first nuclear power plant, after reviewing the various input above and apply the reality in Indonesia as the initial conditions. (author)

Computer aided selection of plant layout | Kitaw | Zede Journal

African Journals Online (AJOL)

This paper deals with the fundamental concepts of plant layout, in which the need for plant layout, the systematic and logical approaches to the problems, layout solutions and the objectives of plant layout are discussed. Further the approaches and the scoring techniques of the two available computer rout ines are ...

Integration of distributed plant process computer systems to nuclear power generation facilities

International Nuclear Information System (INIS)

Bogard, T.; Finlay, K.

1996-01-01

Many operating nuclear power generation facilities are replacing their plant process computer. Such replacement projects are driven by equipment obsolescence issues and associated objectives to improve plant operability, increase plant information access, improve man machine interface characteristics, and reduce operation and maintenance costs. This paper describes a few recently completed and on-going replacement projects with emphasis upon the application integrated distributed plant process computer systems. By presenting a few recent projects, the variations of distributed systems design show how various configurations can address needs for flexibility, open architecture, and integration of technological advancements in instrumentation and control technology. Architectural considerations for optimal integration of the plant process computer and plant process instrumentation ampersand control are evident from variations of design features

Distributed computer control systems in future nuclear power plants

International Nuclear Information System (INIS)

Yan, G.; L'Archeveque, J.V.R.; Watkins, L.M.

1978-09-01

Good operating experience with computer control in CANDU reactors over the last decade justifies a broadening of the role of digital electronic and computer related technologies in future plants. Functions of electronic systems in the total plant context are reappraised to help evolve an appropriate match between technology and future applications. The systems research, development and demonstration program at CRNL is described, focusing on the projects pertinent to the real-time data acquisition and process control requirements. (author)

Plant Layout Analysis by Computer Simulation for Electronic Manufacturing Service Plant

OpenAIRE

Visuwan D.; Phruksaphanrat B

2014-01-01

In this research, computer simulation is used for Electronic Manufacturing Service (EMS) plant layout analysis. The current layout of this manufacturing plant is a process layout, which is not suitable due to the nature of an EMS that has high-volume and high-variety environment. Moreover, quick response and high flexibility are also needed. Then, cellular manufacturing layout design was determined for the selected group of products. Systematic layout planning (SLP) was used to analyze and de...

UCH 3 and 4 plant computer system I/O point summary

International Nuclear Information System (INIS)

Sohn, Kwang Young; Lee, Tae Hoon; Lee, Soon Sung; Lee, Byung Chae; Yoon, Jong Keon; Park, Jeong Suk; Baek, Seung Min; Shin, Hyun Kook

1996-05-01

This technical report summarizes the UCN 3 and 4 I/O database points and is expected to be an important for many disciplines. There are several kind of plant tests before the commercial operation such as Preoperational Test, Cold Hydro Test (CHT), Hot Functional Test (HFT), and Power Ascension Test (PAT). Those are performed in a manner that the validity of the sensor inputs got to the Plant Computer System (PCS) and operational integrity of plant are determined by monitoring the addressable I/O point identification (PID) on the Plant Computer System operator console. For better performance of activities like Emergency Operating Procedure (EOP) computerization, Safety Parameter Display System (SPDS) development, and organizing integrated database for NSSS, referencing the past plant information about I/O database is highly expected. What's more, it is inevitable material for plant system research and general design document work to be done in future. So we present this report based on UCN database for better understanding of plant computer system. 5 refs. (Author) .new

UCH 3 and 4 plant computer system I/O point summary

Energy Technology Data Exchange (ETDEWEB)

Sohn, Kwang Young; Lee, Tae Hoon; Lee, Soon Sung; Lee, Byung Chae; Yoon, Jong Keon; Park, Jeong Suk; Baek, Seung Min; Shin, Hyun Kook [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-05-01

This technical report summarizes the UCN 3 and 4 I/O database points and is expected to be an important for many disciplines. There are several kind of plant tests before the commercial operation such as Preoperational Test, Cold Hydro Test (CHT), Hot Functional Test (HFT), and Power Ascension Test (PAT). Those are performed in a manner that the validity of the sensor inputs got to the Plant Computer System (PCS) and operational integrity of plant are determined by monitoring the addressable I/O point identification (PID) on the Plant Computer System operator console. For better performance of activities like Emergency Operating Procedure (EOP) computerization, Safety Parameter Display System (SPDS) development, and organizing integrated database for NSSS, referencing the past plant information about I/O database is highly expected. What`s more, it is inevitable material for plant system research and general design document work to be done in future. So we present this report based on UCN database for better understanding of plant computer system. 5 refs. (Author) .new.

The Plant-Window system: A flexible, expandable computing environment for the integration of power plant activities

International Nuclear Information System (INIS)

Wood, R.T.; Mullens, J.A.; Naser, J.A.

1994-01-01

Power plant data, and the information that can be derived from it, provide the link to the plant through which the operations, maintenance and engineering staff understand and manage plant performance. The increasing use of computer technology in the US nuclear power industry has greatly expanded the capability to obtain, analyze, and present data about the plant to station personnel. However, it is necessary to transform the vast quantity of available data into clear, concise, and coherent information that can be readily accessed and used throughout the plant. This need can be met by an integrated computer workstation environment that provides the necessary information and software applications, in a manner that can be easily understood and used, to the proper users throughout the plant. As part of a Cooperative Research and Development Agreement with the Electric Power Research Institute, the Oak Ridge National Laboratory has developed functional requirements for a Plant-Wide Integrated Environment Distributed on Workstations (Plant-Window) System. The Plant-Window System (PWS) can serve the needs of operations, engineering, and maintenance personnel at nuclear power stations by providing integrated data and software applications (e.g., monitoring, analysis, diagnosis, and control applications) within a common environment. The PWS requirements identify functional capabilities and provide guidelines for standardized hardware, software, and display interfaces to define a flexible computer environment that permits a tailored implementation of workstation capabilities and facilitates future upgrades

Improving occupational conditions in coal preparation plants considering noise factor. [USSR

Energy Technology Data Exchange (ETDEWEB)

Zhurbinskii, L.F.; Shabel' nikova, E.V.; Sidorov, E.G.

1985-11-01

Three research institutes (IOTT, UkrNIIugleobogashchenie and KuzNIIugleobogashchenie) investigated health hazards associated with noise in coal preparation plants in the Donbass, Kuzbass and Karaganda basins. Investigations showed that there is a close correlation of noise pollution with rate of illness (heart diseases, nervous system diseases, alimentary duct diseases, respiratory diseases and diseases of the auditory organs). An equation which describes the correlation is derived. Correlation coefficient (ranging from 0.75 to 0.94) for each of 4 types of diseases was determined. Analyses showed that reducing noise level from 95 to 85 dB caused a decrease in rate of illness ranging from 2.5 to 3.0 times. Absenteeism due to illness decreased 1.5 to 2.0 times. Investigations also showed that accident rate is influenced by noise level. About 30% of accidents fell on working places with increased noise level. About 10% of accidents fell on working places with noise level of about 85 dB and from 3 to 4% accidents on working places with noise level of about 70 dB. Methods for noise pollution control in coal preparation plants in the USSR are evaluated. Effects of coal transport and handling on noise pollution in coal preparation plants are analyzed.

Supporting plant operation through computer-based procedures

International Nuclear Information System (INIS)

Martinez, Victor; Medrano, Javier; Mendez, Julio

2014-01-01

Digital Systems are becoming more important in controlling and monitoring nuclear power plant operations. The capabilities of these systems provide additional functions as well as support operators in making decisions and avoiding errors. Regarding Operation Support Systems, an important way of taking advantage of these features is using computer-based procedures (CBPs) tools that enhance the plant operation. Integrating digital systems in analogue controls at nuclear power plants in operation becomes an extra challenge, in contrast to the integration of Digital Control Systems in new nuclear power plants. Considering the potential advantages of using this technology, Tecnatom has designed and developed a CBP platform taking currently operating nuclear power plants as its design basis. The result is a powerful tool which combines the advantages of CBPs and the conventional analogue control systems minimizing negative effects during plant operation and integrating operation aid-systems to support operators. (authors)

Preparation and Fluorescent Analysis of Plant Metaphase Chromosomes.

Science.gov (United States)

Schwarzacher, Trude

2016-01-01

Good preparations are essential for informative analysis of both somatic and meiotic chromosomes, cytogenetics, and cell divisions. Fluorescent chromosome staining allows even small chromosomes to be visualized and counted, showing their morphology. Aneuploidies and polyploidies can be established for species, populations, or individuals while changes occurring in breeding lines during hybridization or tissue culture and transformation protocols can be assessed. The process of division can be followed during mitosis and meiosis including pairing and chiasma distribution, as well as DNA organization and structure during the evolution of chromosomes can be studied. This chapter presents protocols for pretreatment and fixation of material, including tips of how to grow plants to get good and healthy meristem with many divisions. The chromosome preparation technique is described using proteolytic enzymes, but acids can be used instead. Chromosome slide preparations are suitable for fluorochrome staining for fast screening (described in the chapter) or fluorescent in situ hybridization (see Schwarzacher and Heslop-Harrison, In situ hybridization. BIOS Scientific Publishers, Oxford, 2000).

9 CFR 590.26 - Egg products entering or prepared in official plants.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Egg products entering or prepared in..., DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Scope of Inspection § 590.26 Egg products entering or prepared in official plants. Eggs and...

Computational Modeling of Auxin: A Foundation for Plant Engineering.

Science.gov (United States)

Morales-Tapia, Alejandro; Cruz-Ramírez, Alfredo

2016-01-01

Since the development of agriculture, humans have relied on the cultivation of plants to satisfy our increasing demand for food, natural products, and other raw materials. As we understand more about plant development, we can better manipulate plants to fulfill our particular needs. Auxins are a class of simple metabolites that coordinate many developmental activities like growth and the appearance of functional structures in plants. Computational modeling of auxin has proven to be an excellent tool in elucidating many mechanisms that underlie these developmental events. Due to the complexity of these mechanisms, current modeling efforts are concerned only with single phenomena focused on narrow spatial and developmental contexts; but a general model of plant development could be assembled by integrating the insights from all of them. In this perspective, we summarize the current collection of auxin-driven computational models, focusing on how they could come together into a single model for plant development. A model of this nature would allow researchers to test hypotheses in silico and yield accurate predictions about the behavior of a plant under a given set of physical and biochemical constraints. It would also provide a solid foundation toward the establishment of plant engineering, a proposed discipline intended to enable the design and production of plants that exhibit an arbitrarily defined set of features.

A Proteomics Sample Preparation Method for Mature, Recalcitrant Leaves of Perennial Plants

Science.gov (United States)

Na, Zhang; Chengying, Lao; Bo, Wang; Dingxiang, Peng; Lijun, Liu

2014-01-01

Sample preparation is key to the success of proteomics studies. In the present study, two sample preparation methods were tested for their suitability on the mature, recalcitrant leaves of six representative perennial plants (grape, plum, pear, peach, orange, and ramie). An improved sample preparation method was obtained: Tris and Triton X-100 were added together instead of CHAPS to the lysis buffer, and a 20% TCA-water solution and 100% precooled acetone were added after the protein extraction for the further purification of protein. This method effectively eliminates nonprotein impurities and obtains a clear two-dimensional gel electrophoresis array. The method facilitates the separation of high-molecular-weight proteins and increases the resolution of low-abundance proteins. This method provides a widely applicable and economically feasible technology for the proteomic study of the mature, recalcitrant leaves of perennial plants. PMID:25028960

A proteomics sample preparation method for mature, recalcitrant leaves of perennial plants.

Directory of Open Access Journals (Sweden)

Deng Gang

Full Text Available Sample preparation is key to the success of proteomics studies. In the present study, two sample preparation methods were tested for their suitability on the mature, recalcitrant leaves of six representative perennial plants (grape, plum, pear, peach, orange, and ramie. An improved sample preparation method was obtained: Tris and Triton X-100 were added together instead of CHAPS to the lysis buffer, and a 20% TCA-water solution and 100% precooled acetone were added after the protein extraction for the further purification of protein. This method effectively eliminates nonprotein impurities and obtains a clear two-dimensional gel electrophoresis array. The method facilitates the separation of high-molecular-weight proteins and increases the resolution of low-abundance proteins. This method provides a widely applicable and economically feasible technology for the proteomic study of the mature, recalcitrant leaves of perennial plants.

Survival and growth of restored Piedmont riparian forests as affected by site preparation, planting stock, and planting aids

Science.gov (United States)

Chelsea M. Curtis; W. Michael Aust; John R. Seiler; Brian D. Strahm

2015-01-01

Forest mitigation sites may have poor survival and growth of planted trees due to poor drainage, compacted soils, and lack of microtopography. The effects of five replications of five forestry mechanical site preparation techniques (Flat, Rip, Bed, Pit, and Mound), four regeneration sources (Direct seed, Bare root, Tubelings, and Gallon), and three planting aids (None...

A computational system for analyze nuclear power plants structures, made by panels, using superelements

International Nuclear Information System (INIS)

Jesus Miranda, C.A. de.

1981-03-01

The analysis of linear static behavior of folded-plate structures like the turbine building of a nuclear power plant by the Finite Element Method. Folded-plate isoparametric plane elements with 48 degrees of freedom each, 8 nodal points, in which shear deformations are considered, and super-elements, whose internal degrees of freedom are condensated, are used. Arbitrary shells can be analized too. A brief exposition of the method is present and the developing of the foregoing element and super-element is also shown. A computer program was developed for the CDC-CYBER 175 computer machine and the FORTRAN IV language was used. The coeficients of the equations system are stored by the technique of block partitioning with a compacted column storage scheme and special attention was dedicated to the preparation of the problem's data and some options were developed for this purpose. (Author) [pt

V-1 nuclear power plant standby RPP-16S computer software

International Nuclear Information System (INIS)

Suchy, R.

1988-01-01

The software structure of the function of program modules of the RPP-16S standby computer which is part of the information system of the V-1 Bohunice nuclear power plant are described. The multitasking AMOS operational system is used for the organization of programs in the computer. The program modules are classified in five groups by function, i.e., in modules for the periodical collection of values and for the measurement of process quantities for both nuclear power plant units; for the primary processing of the values; for the monitoring of exceedance of preset limits; for unit operators' communication with the computer. The fifth group consists of users program modules. The standby computer software was tested in the actual operating conditions of the V-1 power plant. The results showed it operated correctly; minor shortcomings were removed. (Z.M.). 1 fig

Computer graphics as an information means for power plants

International Nuclear Information System (INIS)

Kollmannsberger, J.; Pfadler, H.

1990-01-01

Computer-aided graphics have proved increasingly successful as a help in process control in large plants. The specific requirements for the system and the methods of planning and achieving graphic systems in powerstation control rooms are described. Experience from operation is evaluated from completed plants. (orig.) [de

High degree utilization of computers for design of nuclear power plants

International Nuclear Information System (INIS)

Masui, Takao; Sawada, Takashi

1992-01-01

Nuclear power plants are the huge technology in which various technologies are compounded, and the high safety is demanded. Therefore, in the design of nuclear power plants, it is necessary to carry out the design by sufficiently grasping the behavior of the plants, and to confirm the safety by carrying out the accurate design evaluation supposing the various operational conditions, and as the indispensable tool for these analysis and evaluation, the most advanced computers in that age have been utilized. As to the utilization for the design, there are the fields of design, analysis and evaluation and another fields of the application to the support of design. Also in the field of the application to operation control, computers are utilized. The utilization of computers for the core design, hydrothermal design, core structure design, safety analysis and structural analysis of PWR plants, and for the nuclear design, safety analysis and heat flow analysis of FBR plants, the application to the support of design and the application to operation control are explained. (K.I.)

Fail-safe computer-based plant protection systems

International Nuclear Information System (INIS)

Keats, A.B.

1983-01-01

A fail-safe mode of operation for computers used in nuclear reactor protection systems was first evolved in the UK for application to a sodium cooled fast reactor. The fail-safe properties of both the hardware and the software were achieved by permanently connecting test signals to some of the multiplexed inputs. This results in an unambiguous data pattern, each time the inputs are sequentially scanned by the multiplexer. The ''test inputs'' simulate transient excursions beyond defined safe limits. The alternating response of the trip algorithms to the ''out-of-limits'' test signals and the normal plant measurements is recognised by hardwired pattern recognition logic external to the computer system. For more general application to plant protection systems, a ''Test Signal Generator'' (TSG) is used to compute and generate test signals derived from prevailing operational conditions. The TSG, from its knowledge of the sensitivity of the trip algorithm to each of the input variables, generates a ''test disturbance'' which is superimposed upon each variable in turn, to simulate a transient excursion beyond the safe limits. The ''tripped'' status yielded by the trip algorithm when using data from a ''disturbed'' input forms part of a pattern determined by the order in which the disturbances are applied to the multiplexer inputs. The data pattern formed by the interleaved test disturbances is again recognised by logic external to the protection system's computers. This fail-safe mode of operation of computer-based protection systems provides a powerful defence against common-mode failure. It also reduces the importance of software verification in the licensing procedure. (author)

Utilization of logistic computer programs in the power plant piping industry

International Nuclear Information System (INIS)

Motzel, E.

1982-01-01

Starting from the general situation of the power plant piping industry, the utilization of computer programs as well as the specific magnitude of complexity connected with the project realisation, the necessity for using logistic computer programs especially in case of nuclear power plants is explained. The logistic term as well as the logistic data are described. At the example of the nuclear power plant KRB II, Gundremmingen, Block B/C the practical use of such programs is shown. The planning, scheduling and supervision is carried out computer-aided by means of network-technique. The material management, prefabrication, installation including management of certificates for welding and testing activities is planned and controlled by computer programs as well. With the piping systems installed a complete erection work documentation is available which also serves as base for the billing versus the client. The budgeted costs are continuously controlled by means of a cost control program. Summing-up the further development in controlling piping contracts computer-supported is described with regard to software, hardware and the organisation structure. Furthermore the concept of a self-supporting field computer is introduced for the first time. (orig.) [de

The computer program system for structural design of nuclear power plants

International Nuclear Information System (INIS)

Aihara, S.; Atsumi, K.; Sasagawa, K.; Satoh, S.

1979-01-01

In recent days, the design method of the Nuclear Power Plant has become more complex than in the past. The Finite Element Method (FEM) applied for analysis of Nuclear Power Plants, especially requires more computer use. The recent computers have made remarkable progress, so that in design work manpower and time necessary for analysis have been reduced considerably. However, instead the arrangement of outputs have increased tremendously. Therefore, a computer program system was developed for performing all of the processes, from data making to output arrangement, and rebar evaluations. This report introduces the computer program system pertaining to the design flow of the Reactor Building. (orig.)

Use of computers at nuclear power plants

International Nuclear Information System (INIS)

Sen'kin, V.I.; Ozhigano, Yu.V.

1974-01-01

Applications of information and control computors in reacter central systems in Great Britain, Federal Republic of Germany, France, Canada, and the USA is surveyed. For the purpose of increasing the reliability of the computers effective means were designed for emergency operation and automatic computerized controls, and highly reliable micromodel modifications were developed. Numerical data units were handled along with development of methods and diagrams for converting analog values to numerical values, in accordance with modern requirements. Some data are presented on computer reliability in operating nuclear power plants both proposed and under construction. It is concluded that in foreign nuclear power stations the informational and calculational computers are finding increasingly wide distribution. Rapid action, the possibility of controlling large parameters, and operation of the computer in conjunction with increasing reliability are speeding up the process of introducing computers in atomic energy and broadenig their functions. (V.P.)

IAEA activities in preparation of reglamentary documents on nuclear power plant safety

International Nuclear Information System (INIS)

Konstantinov, L.V.

1976-01-01

The activities of the IAEA in the field of working out practical rules and recommendations ensuring the nuclear power plant safety are discussed. The practical rules will establish the aims and the minimum of requirements, that must be carried out to ensure the necessary safety of systems, components and equipment of the nuclear power plant throughout the whole period of its exploitation. Described is the procedure of the document preparation, consisting of the collection of documents, edited in different countries, the integration of documents by the IAEA Secretariat, the consideratiom of documents by the Group of senior advisers, the preparation of the draft document, the additional wort at the document in accordaqce with the remarks of the IAEA member-countries, the edition and dissemination of documents. The necessity for the active participation of the CMEA member-countries in the development and discussion of documents concerning the nuclear power plant safety is stated [ru

Practical application of computer graphics in nuclear power plant engineering

International Nuclear Information System (INIS)

Machiba, Hiroshi; Kawamura, Hirobumi; Sasaki, Norio

1992-01-01

A nuclear power plant is composed of a vast amount of equipment, piping, and so on, and six or seven years are required to complete the design and engineering from the initial planning stage to the time of commercial operation. Furthermore, operating plants must be continually maintained and improved for a long period. Computer graphics were first applied to the composite arrangement design of nuclear power plants in the form of 3-dimensional CAD. Subsequently, as the introduction of CAE has progressed, a huge assortment of information has been accumulated in database, and measures have been sought that would permit the convenient utilization of this information. Using computer graphics technologies, improvement of the interface between the user and such databases has recently been accomplished. In response to the growth in environmental consciousness, photo-realistic simulations for artistic design of the interior and overviews showing harmony with the surroundings have been achieved through the application of computer graphics. (author)

Future trends in power plant process computer techniques

International Nuclear Information System (INIS)

Dettloff, K.

1975-01-01

The development of new concepts of the process computer technique has advanced in great steps. The steps are in the three sections: hardware, software, application concept. New computers with a new periphery such as, e.g., colour layer equipment, have been developed in hardware. In software, a decisive step in the sector 'automation software' has been made. Through these components, a step forwards has also been made in the question of incorporating the process computer in the structure of the whole power plant control technique. (orig./LH) [de

Bid Preparation and Evaluation for Nuclear Power Plant Project Management

International Nuclear Information System (INIS)

Mohd Idris Taib, Mohd Khairulezwan Abdul Manan and Nur Farizan Amadzun

2011-01-01

Bid preparation and evaluation is one of the main activities in Nuclear Power Plant Project management. International Atomic Energy Agency guide and Korean experience was studied for Malaysian requirement in realization of first Nuclear Power Plant. Several aspects shall be taken into consideration such as political scenario, financial capabilities, sitting, human resource, technologies, fuel supplies and decommissioning for long term exceeded hundred years. Bidding process and activities is proposed for our country requirement. The main activities included but unlimited to Bid Invitation Specification, Bid Evaluation Process, Technical Evaluation, Economic Bid Evaluation and Contracting. On the end of day, Malaysia need safe and reliable Nuclear Power Plant. Malaysian Economic Transformation Programme also get benefit from spin-off localization products and services as well as Technology Transfer Programme. (author)

Plants and Human Affairs: Educational Enhancement Via a Computer.

Science.gov (United States)

Crovello, Theodore J.; Smith, W. Nelson

To enhance both teaching and learning in an advanced undergraduate elective course on the interrelationships of plants and human affairs, the computer was used for information retrieval, multiple choice course review, and the running of three simulation models--plant related systems (e.g., the rise in world coffee prices after the 1975 freeze in…

Nuclear plant operations, maintenance, and configuration management using three-dimensional computer graphics and databases

International Nuclear Information System (INIS)

Tutos, N.C.; Reinschmidt, K.F.

1987-01-01

Stone and Webster Engineering Corporation has developed the Plant Digital Model concept as a new approach to Configuration Mnagement of nuclear power plants. The Plant Digital Model development is a step-by-step process, based on existing manual procedures and computer applications, and is fully controllable by the plant managers and engineers. The Plant Digital Model is based on IBM computer graphics and relational database management systems, and therefore can be easily integrated with existing plant databases and corporate management-information systems

Evaluation of Root Canal Preparation Using Rotary System and Hand Instruments Assessed by Micro-Computed Tomography

Science.gov (United States)

Stavileci, Miranda; Hoxha, Veton; Görduysus, Ömer; Tatar, Ilkan; Laperre, Kjell; Hostens, Jeroen; Küçükkaya, Selen; Muhaxheri, Edmond

2015-01-01

Background Complete mechanical preparation of the root canal system is rarely achieved. Therefore, the purpose of this study was to evaluate and compare the root canal shaping efficacy of ProTaper rotary files and standard stainless steel K-files using micro-computed tomography. Material/Methods Sixty extracted upper second premolars were selected and divided into 2 groups of 30 teeth each. Before preparation, all samples were scanned by micro-computed tomography. Thirty teeth were prepared with the ProTaper system and the other 30 with stainless steel files. After preparation, the untouched surface and root canal straightening were evaluated with micro-computed tomography. The percentage of untouched root canal surface was calculated in the coronal, middle, and apical parts of the canal. We also calculated straightening of the canal after root canal preparation. Results from the 2 groups were statistically compared using the Minitab statistical package. Results ProTaper rotary files left less untouched root canal surface compared with manual preparation in coronal, middle, and apical sector (protary techniques completely prepared the root canal, and both techniques caused slight straightening of the root canal. PMID:26092929

Further improvement in ABWR (part-4) open distributed plant process computer system

International Nuclear Information System (INIS)

Makino, Shigenori; Hatori, Yoshinori

1999-01-01

In the nuclear industry of Japan, the electric power companies have promoted the plant process computer (PPC) technology of nuclear power plant (NPP). When PPC was introduced to NPP for the first time, because of very tight requirement such as high reliability, high speed processing, the large-scale customized computer was applied. As for recent computer field, the large market of computer contributes to the remarkable progress of engineering work station (EWS) and personal computer (PC) technology. Moreover because the data transmission technology has been progressing at the same time, world wide computer network has been established. Thanks to progress of both technologies, the distributed computer system has been established at reasonable price. So Tokyo Electric Power Company (TEPCO) is trying to apply it for PPC of NPP. (author)

Evaluation of Root Canal Preparation Using Rotary System and Hand Instruments Assessed by Micro-Computed Tomography.

Science.gov (United States)

Stavileci, Miranda; Hoxha, Veton; Görduysus, Ömer; Tatar, Ilkan; Laperre, Kjell; Hostens, Jeroen; Küçükkaya, Selen; Muhaxheri, Edmond

2015-06-20

Complete mechanical preparation of the root canal system is rarely achieved. Therefore, the purpose of this study was to evaluate and compare the root canal shaping efficacy of ProTaper rotary files and standard stainless steel K-files using micro-computed tomography. Sixty extracted upper second premolars were selected and divided into 2 groups of 30 teeth each. Before preparation, all samples were scanned by micro-computed tomography. Thirty teeth were prepared with the ProTaper system and the other 30 with stainless steel files. After preparation, the untouched surface and root canal straightening were evaluated with micro-computed tomography. The percentage of untouched root canal surface was calculated in the coronal, middle, and apical parts of the canal. We also calculated straightening of the canal after root canal preparation. Results from the 2 groups were statistically compared using the Minitab statistical package. ProTaper rotary files left less untouched root canal surface compared with manual preparation in coronal, middle, and apical sector (p<0.001). Similarly, there was a statistically significant difference in root canal straightening after preparation between the techniques (p<0.001). Neither manual nor rotary techniques completely prepared the root canal, and both techniques caused slight straightening of the root canal.

EMI Evaluation on Wireless Computer Devices in Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Jae Ki; JI Yeong Hwa; Sung, Chan Ho

2011-01-01

Wireless computer devices, for example, mice and keyboards are widely used in various industries. However, I and C (instrumentation and control) equipment in nuclear power plants are very susceptible to the EMI (Electro-magnetic interference) and there are concerns regarding EMI induced transient caused by wireless computer devices which emit electromagnetic waves for communication. In this paper, industrial practices and nuclear related international standards are investigated to verify requirements of wireless devices. In addition, actual measurement and evaluation for the intensity of EMI of some commercially available wireless devices is performed to verify their compatibility in terms of EMI. Finally we suggest an appropriate method of using wireless computer devices in nuclear power plant control rooms for better office circumstances of operators

Elaboration of natural polyfunctional preparations with antiparasitic and biostimulating properties for plant growing.

Science.gov (United States)

Iutynska, G O

2012-01-01

Producer of macrolide antibiotic avermectin Streptomyces avermitilis UCM Ac-2179 has been isolated from Ukrainian chernozem soil, its biosynthetic activity has been increased by the traditional selection and chemical mutagenesis methods. Streptomyces avermitilis UCM Ac-2179 synthesizes avermectin with the content of anti-parasitic B-components more than 40%. Addition of exogenous Na-pyruvate (1.5 mg/L) in cultural medium promotes a 2.5-fold augmentation of the avermectin synthesis. The preparation Avercom has been obtained by the method of ethanol extraction from the producer biomass. This preparation includes antibiotic avermectin and other biologically active substances: free amino acids, lipids, phytohormones. Avercom has high nematicidic activity and raises plant resistance to fungal and viral diseases. On the base of Avercom and plant growth regulators the complex preparations Actinolan and Ascoldia have been elaborated. The effectiveness of the biopreparations as nematicidic and plantstimulating means under experimental and industrial conditions was confirmed.

Optimizing the roles of man and computer in nuclear power plant control

International Nuclear Information System (INIS)

Colley, R.W.; Seeman, S.E.

1983-10-01

We are presently participating in a program to optimize the functional man-machine interface for Liquid Metal-Cooled Fast Breeder Reactors. The overall objective of this program is to enhance operational safety; that is, to accommodate plant incidents through optimal integration of man and machine in performing the functions required to safely control a plant during both normal and off-normal conditions. Purpose of this talk is to describe an approach to determine the optimal roles of man and computer in the control of nuclear power plants. Purpose of this session was to get together people that are working in the areas of understanding of how operators control plants, and working on developing new aids for these operators. We were asked to explain how our modeling and approach we're taking will lead us to an optimization of the roles of the man and the computer in the control of nuclear power plants. Our emphasis was to be on the functions required for plant control, and how the attributes of the human operator and the attributes of the computer can be optimally used to enhance operational safety in performing these functions

Situation awareness and trust in computer-based procedures in nuclear power plant operations

Energy Technology Data Exchange (ETDEWEB)

Throneburg, E. B.; Jones, J. M. [AREVA NP Inc., 7207 IBM Drive, Charlotte, NC 28262 (United States)

2006-07-01

Situation awareness and trust are two issues that need to be addressed in the design of computer-based procedures for nuclear power plants. Situation awareness, in relation to computer-based procedures, concerns the operators' knowledge of the plant's state while following the procedures. Trust concerns the amount of faith that the operators put into the automated procedures, which can affect situation awareness. This paper first discusses the advantages and disadvantages of computer-based procedures. It then discusses the known aspects of situation awareness and trust as applied to computer-based procedures in nuclear power plants. An outline of a proposed experiment is then presented that includes methods of measuring situation awareness and trust so that these aspects can be analyzed for further study. (authors)

Situation awareness and trust in computer-based procedures in nuclear power plant operations

International Nuclear Information System (INIS)

Throneburg, E. B.; Jones, J. M.

2006-01-01

Situation awareness and trust are two issues that need to be addressed in the design of computer-based procedures for nuclear power plants. Situation awareness, in relation to computer-based procedures, concerns the operators' knowledge of the plant's state while following the procedures. Trust concerns the amount of faith that the operators put into the automated procedures, which can affect situation awareness. This paper first discusses the advantages and disadvantages of computer-based procedures. It then discusses the known aspects of situation awareness and trust as applied to computer-based procedures in nuclear power plants. An outline of a proposed experiment is then presented that includes methods of measuring situation awareness and trust so that these aspects can be analyzed for further study. (authors)

The modernization of the process computer of the Trillo Nuclear Power Plant

International Nuclear Information System (INIS)

Martin Aparicio, J.; Atanasio, J.

2011-01-01

The paper describes the modernization of the Process computer of the Trillo Nuclear Power Plant. The process computer functions, have been incorporated in the non Safety I and C platform selected in Trillo NPP: the Siemens SPPA-T2000 OM690 (formerly known as Teleperm XP). The upgrade of the Human Machine Interface of the control room has been included in the project. The modernization project has followed the same development process used in the upgrade of the process computer of PWR German nuclear power plants. (Author)

A personal computer code for seismic evaluations of nuclear power plant facilities

International Nuclear Information System (INIS)

Xu, J.; Graves, H.

1991-01-01

In the process of review and evaluation of licensing issues related to nuclear power plants, it is essential to understand the behavior of seismic loading, foundation and structural properties and their impact on the overall structural response. In most cases, such knowledge could be obtained by using simplified engineering models which, when properly implemented, can capture the essential parameters describing the physics of the problem. Such models do not require execution on large computer systems and could be implemented through a personal computer (PC) based capability. Recognizing the need for a PC software package that can perform structural response computations required for typical licensing reviews, the US Nuclear Regulatory Commission sponsored the development of a PC operated computer software package CARES (Computer Analysis for Rapid Evaluation of Structures) system. This development was undertaken by Brookhaven National Laboratory (BNL) during FY's 1988 and 1989. A wide range of computer programs and modeling approaches are often used to justify the safety of nuclear power plants. It is often difficult to assess the validity and accuracy of the results submitted by various utilities without developing comparable computer solutions. Taken this into consideration, CARES is designed as an integrated computational system which can perform rapid evaluations of structural behavior and examine capability of nuclear power plant facilities, thus CARES may be used by the NRC to determine the validity and accuracy of analysis methodologies employed for structural safety evaluations of nuclear power plants. CARES has been designed to operate on a PC, have user friendly input/output interface, and have quick turnaround. This paper describes the various features which have been implemented into the seismic module of CARES version 1.0

Modernization of the plant computer C. N. Cofrentes

International Nuclear Information System (INIS)

Sanchez, M.; Zuriaga, J. V.

2011-01-01

Cofrentes NPP C and I systems modernization plan identifies a number of systems which upgrade is a priority mainly because of obsolescence criteria and the need for technological improvement. In 2009, the Turbine and Bypass Control Systems modernization project concluded successfully, paving the way for updating the big brother of Cofrentes NPP, the Plant Process Computer, which is connected to all process systems to collect data, store, analyze and present them to the end user in any plant operational mode. (Author)

Graph-state preparation and quantum computation with global addressing of optical lattices

International Nuclear Information System (INIS)

Kay, Alastair; Pachos, Jiannis K.; Adams, Charles S.

2006-01-01

We present a way to manipulate ultracold atoms where four atomic levels are trapped by appropriately tuned optical lattices. When employed to perform quantum computation via global control, this unique structure dramatically reduces the number of steps involved in the control procedures, either for the standard, network, model, or for one-way quantum computation. The use of a far-blue-detuned lattice and a magnetically insensitive computational basis makes the scheme robust against decoherence. The present scheme is a promising candidate for experimental implementation of quantum computation and for graph-state preparation in one, two, or three spatial dimensions

Preparation of substituting seaweed field mounds accompanying site preparation for No.3 plant in Ikata Nuclear Power Station

International Nuclear Information System (INIS)

Ishihara, Hisashi; Oshima, Teruhiko; Fujisaki, Yuichi; Saeki, Taketoshi

1987-01-01

Shikoku Electric Power Co., Inc. is constructing No.3 plant adjacently to No.1 and No.2 plants in operation in Ikata Nuclear Power Station. In the coastal area of Iyo-nada, many seaweed fields are distributed, which are important biologically and for fishery. In the works of site preparation for No.3 plant, a part of the site is created by reclamation of sea area, therefore the natural seaweed fields in the area disappear. From the viewpoint of various circumstances and environment preservation, it was decided to create about 60,000 m 2 of seaweed field mounds on the seabed around the site as the substitute for disappearing natural seaweed fields. The Seaweed Field Study Group composed of the men of learning and experience was organized to obtain the guidance on the possibility of creating artificial seaweed fields, the techniques for creation and the effect on environment accompanying the creation of mounds. The creation works were started in October, 1985, and are in progress smoothly utilizing effectively the stones and rocks cut in the site preparation works. The topographic and geological features, sea conditions, the present state of seaweed fields, the experiment on creating artificial seaweed fields, the design and construction of mounds and others are reported. (Kako, I.)

Three-dimensional computer aided design system for plant layout

International Nuclear Information System (INIS)

Yoshinaga, Toshiaki; Kiguchi, Takashi; Tokumasu, Shinji; Kumamoto, Kenjiro.

1986-01-01

The CAD system for three-dimensional plant layout planning, with which the layout of pipings, cable trays, air conditioning ducts and so on in nuclear power plants can be planned and designed effectively in a short period is reported. This system comprises the automatic routing system by storing the rich experience and know-how of designers in a computer as the knowledge, and deciding the layout automatically following the predetermined sequence by using these, the interactive layout system for reviewing the routing results from higher level and modifying to the optimum layout, the layout evaluation system for synthetically evaluating the layout from the viewpoint of the operability such as checkup and maintenance, and the data base system which enables these effective planning and design. In this report, the total constitution of this system and the technical features and effects of the individual subsystems are outlined. In this CAD system for three-dimensional plant layout planning, knowledge engineering, CAD/CAM, computer graphics and other latest technology were introduced, accordingly by applying this system to plant design, the design can be performed quickly, various case studies can be carried out at planning stage, and systematic and optimum layout planning becomes possible. (Kako, I.)

Traditional Preparations and Methanol Extracts of Medicinal Plants from Papua New Guinea Exhibit Similar Cytochrome P450 Inhibition

Directory of Open Access Journals (Sweden)

Erica C. Larson

2016-01-01

Full Text Available The hypothesis underlying this current work is that fresh juice expressed from Papua New Guinea (PNG medicinal plants (succus will inhibit human Cytochrome P450s (CYPs. The CYP inhibitory activity identified in fresh material was compared with inhibition in methanol extracts of dried material. Succus is the most common method of traditional medicine (TM preparation for consumption in PNG. There is increasing concern that TMs might antagonize or complicate drug therapy. We have previously shown that methanol extracts of commonly consumed PNG medicinal plants are able to induce and/or inhibit human CYPs in vitro. In this current work plant succus was prepared from fresh plant leaves. Inhibition of three major CYPs was determined using human liver microsomes and enzyme-selective model substrates. Of 15 species tested, succus from 6/15 was found to inhibit CYP1A2, 7/15 inhibited CYP3A4, and 4/15 inhibited CYP2D6. Chi-squared tests determined differences in inhibitory activity between succus and methanol preparations. Over 80% agreement was found. Thus, fresh juice from PNG medicinal plants does exhibit the potential to complicate drug therapy in at risk populations. Further, the general reproducibility of these findings suggests that methanol extraction of dried material is a reasonable surrogate preparation method for fresh plant samples.

Cyber Security on Nuclear Power Plant's Computer Systems

International Nuclear Information System (INIS)

Shin, Ick Hyun

2010-01-01

Computer systems are used in many different fields of industry. Most of us are taking great advantages from the computer systems. Because of the effectiveness and great performance of computer system, we are getting so dependable on the computer. But the more we are dependable on the computer system, the more the risk we will face when the computer system is unavailable or inaccessible or uncontrollable. There are SCADA, Supervisory Control And Data Acquisition, system which are broadly used for critical infrastructure such as transportation, electricity, water management. And if the SCADA system is vulnerable to the cyber attack, it is going to be nation's big disaster. Especially if nuclear power plant's main control systems are attacked by cyber terrorists, the results may be huge. Leaking of radioactive material will be the terrorist's main purpose without using physical forces. In this paper, different types of cyber attacks are described, and a possible structure of NPP's computer network system is presented. And the paper also provides possible ways of destruction of the NPP's computer system along with some suggestions for the protection against cyber attacks

Analysis of steam generator behaviour in nuclear power plant with computer program RELAP5; Analiza delovanja uparjalnika jedrske elektrarne s programom RELAP5

Energy Technology Data Exchange (ETDEWEB)

Zeljko, M; Gregoric, M; Peterlin, G [Institut ' Jozef Stefan' , Ljubljana (Yugoslavia)

1983-07-01

Analyses of nuclear power plant behaviour are made with large computer programs. We used RELAP5/MOD1/CYCLE001, which was developed in Idaho National Engineering laboratory. Input model was prepared to analyze transients in steam generator of NPP Krsko. We found out that this version had a lot of faults so we intend to implement a new cycle. First experience shows the whole complexity of such analysis from technical and economical viewpoints. (author)

Cognitive models and computer aids for nuclear plant control room operators

International Nuclear Information System (INIS)

Sheridan, T.B.

1982-01-01

This paper reviews what is usually meant by a cognitive model of a control room operator in a nuclear power plant. It emphasizes the idea of internal (that is, mental) representation of external events and the use of such representation for the cognitive steps of attending, recognizing or learning, assessing and deciding. As computers play an increasingly important role in nuclear power plants, especially as cognitive aids to human supervisors of highly automated control systems, it is important that the software and computer interface characteristics be compatible with the operator's internal model. Specific examples discussed in this paper are in the monitoring and prediction of the plant state and in the detection and diagnosis of failures. Current trends in SPDS (safety parameter display system) and failure detection/location systems will be discussed in this regard

Effective handling of software anomalies in computer based systems at nuclear power plants. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

International Nuclear Information System (INIS)

2000-03-01

This report reviews possible types of anomalies that are related to software in nuclear power plants, outlines techniques that can be used to identify anomalies throughout the entire software life-cycle, and discusses important issues that must be considered during anomaly investigation and resolution. Typically, anomalies are identified, investigated and resolved during the normal process of developing or maintaining plant software, where these activities are covered by procedures and tools that are part of this process. Nevertheless, to reduce the number and impact of anomalies under plant operating conditions, it is important to ensure that good plans, procedures and tools are in place throughout the software life-cycle. The need for this was pointed out by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). The report is the result of a series of consultants meetings held by the IAEA in 1997 and 1998 in Vienna. It was prepared with the participation and contributions of experts from Austria, Canada, Germany, Hungary, the United Kingdom and the United States of America. The scope of activities described in this report covers a methodology for anomaly identification, anomaly investigation and anomaly resolution. The activities to be done within these steps strongly depend on the safety category of the software, the actual life-cycle phase of the software, the type of the software and the severity of the anomaly

ceRNAs in plants: computational approaches and associated challenges for target mimic research.

Science.gov (United States)

Paschoal, Alexandre Rossi; Lozada-Chávez, Irma; Domingues, Douglas Silva; Stadler, Peter F

2017-05-30

The competing endogenous RNA hypothesis has gained increasing attention as a potential global regulatory mechanism of microRNAs (miRNAs), and as a powerful tool to predict the function of many noncoding RNAs, including miRNAs themselves. Most studies have been focused on animals, although target mimic (TMs) discovery as well as important computational and experimental advances has been developed in plants over the past decade. Thus, our contribution summarizes recent progresses in computational approaches for research of miRNA:TM interactions. We divided this article in three main contributions. First, a general overview of research on TMs in plants is presented with practical descriptions of the available literature, tools, data, databases and computational reports. Second, we describe a common protocol for the computational and experimental analyses of TM. Third, we provide a bioinformatics approach for the prediction of TM motifs potentially cross-targeting both members within the same or from different miRNA families, based on the identification of consensus miRNA-binding sites from known TMs across sequenced genomes, transcriptomes and known miRNAs. This computational approach is promising because, in contrast to animals, miRNA families in plants are large with identical or similar members, several of which are also highly conserved. From the three consensus TM motifs found with our approach: MIM166, MIM171 and MIM159/319, the last one has found strong support on the recent experimental work by Reichel and Millar [Specificity of plant microRNA TMs: cross-targeting of mir159 and mir319. J Plant Physiol 2015;180:45-8]. Finally, we stress the discussion on the major computational and associated experimental challenges that have to be faced in future ceRNA studies. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Study on standard coal preparation plant for coking coal in Jharia Coalfield

Energy Technology Data Exchange (ETDEWEB)

Winiewski, J; Sarkar, G G

1975-10-01

The proposed standardization of coal preparation plant will be based on three standard types of crushing station, a standard jig washery or cyclone washery, and three standard types of slurry water treatment section. Some large installations, and some existing washeries after modification, may incorporate heavy media baths for coarse coal and jigs for slack coal, where coal is easy or moderately easy to wash. Flow sheets are given for the standard types of crushing plant, washery, and slurry water circuit. The storage of raw coal and saleable products is briefly discussed.

Computer Forensic Function Testing: Media Preparation, Write Protection And Verification

Directory of Open Access Journals (Sweden)

Yinghua (David Guo

2010-06-01

Full Text Available Normal 0 false false false EN-US JA AR-SA The growth in the computer forensic field has created a demand for new software (or increased functionality to existing software and a means to verify that this software is truly forensic i.e. capable of meeting the requirements of the trier of fact. In this work, we review our previous work---a function oriented testing framework for validation and verification of computer forensic tools. This framework consists of three parts: function mapping, requirements specification and reference set development. Through function mapping, we give a scientific and systemical description of the fundamentals of computer forensic discipline, i.e. what functions are needed in the computer forensic investigation process. We focus this paper on the functions of media preparation, write protection and verification. Specifically, we complete the function mapping of these functions and specify their requirements. Based on this work, future work can be conducted to develop corresponding reference sets to test any tools that possess these functions.

Application of control computer system TESLA RPP-16 in the Bohunice nuclear power plant

International Nuclear Information System (INIS)

Spetko, V.

1976-01-01

The reasons are given for the installation of a computer at the A-1 nuclear power plant in Czechoslovakia with regard to applied research. The configuration, placement, and software of the computer system is described. The programmes are written in the SAM and FORTRAN-IV languages. The knowledge acquired in the course of tests and the prospect of the future installation of computer control equipment in the A-1 nuclear power plant are described. (J.P.)

Advanced digital computers, controls, and automation technologies for power plants: Proceedings

International Nuclear Information System (INIS)

Bhatt, S.C.

1992-08-01

This document is a compilation of the papers that were presented at an EPRI workshop on Advances in Computers, Controls, and Automation Technologies for Power Plants. The workshop, sponsored by EPRI's Nuclear Power Division, took place February 1992. It was attended by 157 representatives from electric utilities, equipment manufacturers, engineering consulting organizations, universities, national laboratories, government agencies and international utilities. More than 40% of the attendees were from utilities representing the majority group. There were 30% attendees from equipment manufacturers and the engineering consulting organizations. The participants from government agencies, universities, and national laboratories were about 10% each. The workshop included a keynote address, 35 technical papers, and vendor's equipment demonstrations. The technical papers described the state-of-the-art in the areas of recent utility digital upgrades such as digital feedwater controllers, steam generator level controllers, integrated plant computer systems, computer aided diagnostics, automated testing and surveillance and other applications. A group of technical papers presented the ongoing B ampersand W PWR integrated plant control system prototype developments with the triple redundant advanced digital control system. Several international papers from France, Japan and U.K. presented their programs on advance power plant design and applications. Significant advances in the control and automation technologies such as adaptive controls, self-tuning methods, neural networks and expert systems were presented by developers, universities, and national laboratories. Individual papers are indexed separately

Aspects regarding computer control of 15 N separation plant

International Nuclear Information System (INIS)

Kaucsar, M.; Cosma, V.; Axente, D.; Baldea, A.; Bendea, H.; Bunea, V

2001-01-01

In order to improve the efficiency of a separation plant the whole process must be automatically controlled. The plant has a single output - the isotopic product. This output is characterized by a complex function, which involves qualitative or/and quantitative properties of the product. There are two important inputs into the system, namely: the amount of the substances and compounds which supply the plant and the electric power consumption. Our first aim is to reduce the input/output ratio of the separation plant. On the other hand, by applying this automatic control system we can reduce the operating personnel also. The isotopic product is sampled and analyzed using a dedicated mass spectrometer. An overall closed loop through the separation plant including this mass spectrometer could be very efficient, but the theoretical analysis is too complex and it is very difficult to realize it in practice. Therefore, multiple local control loops are preferred to apply for each product correlated parameter. Between these parameters there are complex interdependencies, governed by differential equations. The computer is equipped with standard input/output hardware, but in order to use it in the complex feedback loops, extra input/output hardware must be added, namely, dedicated input/output module cards. Depending on the operating principle of the detectors and actuators the signals involved in the whole system are analog and digital. The majority of the sensors and transducers generates analog signals and only a few of them have digital output. The last case is typical for transducers specialized mainly for detecting the level of a parameter. Actuators also need analog or digital control signals, corresponding to their operating principles. The computer control of isotopic plant has a great advantage of being very flexible in implementing adequate control software with operator friendly interfacing routines. (authors)

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

A first accident simulation for Angra-1 power plant using the ALMOD computer code

International Nuclear Information System (INIS)

Camargo, C.T.M.

1981-02-01

The acquisition of the Almod computer code from GRS-Munich to CNEN has permited doing calculations of transients in PWR nuclear power plants, in which doesn't occur loss of coolant. The implementation of the german computer code Almod and its application in the calculation of Angra-1, a nuclear power plant different from the KWU power plants, demanded study and models adaptation; and due to economic reasons simplifications and optimizations were necessary. The first results define the analytical potential of the computer code, confirm the adequacy of the adaptations done and provide relevant conclusions about the Angra-1 safety analysis, showing at the same time areas in which the model can be applied or simply improved. (Author) [pt

Soft computing for fault diagnosis in power plants

International Nuclear Information System (INIS)

Ciftcioglu, O.; Turkcan, E.

1998-01-01

Considering the advancements in the AI technology, there arises a new concept known as soft computing. It can be defined as the processing of uncertain information with the AI methods, that refers to explicitly the methods using neural networks, fuzzy logic and evolutionary algorithms. In this respect, soft computing is a new dimension in information processing technology where linguistic information can also be processed in contrast with the classical stochastic and deterministic treatments of data. On one hand it can process uncertain/incomplete information and on the other hand it can deal with non-linearity of large-scale systems where uncertainty is particularly relevant with respect to linguistic information and incompleteness is related to fault tolerance in fault diagnosis. In this perspective, the potential role of soft computing in power plant operation is presented. (author)

Multi-fields' coordination information integrated platform for nuclear power plant operation preparation

International Nuclear Information System (INIS)

Yuan Chang; Li Yong; Ye Zhiqiang

2011-01-01

To realize the coordination in multi-fields' work and information sharing, by applying the method of Enterprise Architecture (EA), the business architecture, functional flow and application architecture of Nuclear Power Plant's operation preparation information integrated platform are designed, which can realize the information sharing and coordination of multi fields. (authors)

Computer aided process planning at the Oak Ridge Y-12 plant: a pilot project

International Nuclear Information System (INIS)

Hewgley, R.E. Jr.; Prewett, H.P. Jr.

1979-01-01

In 1976, a formal needs analysis was conducted in one of the Fabrication Division Shops of all activities from the receipt of an order through final machining. The results indicated deficiencies in process planning activities involving special production work. A pilot program was organized to investigate the benefits of emerging CAM technology and application of GT concepts for machining operations at the Y-12 Plant. The objective of the CAPP Project was to provide computer-assisted process planning for special production machining in th shop. The CAPP team was charged with the specific goal of demonstrating computer-aided process planning within a four-year term. The CAPP charter included a plan with intermediate measurable milestones for achieving its mission. In three years, the CAPP project demonstrated benefits to process planning. A capability to retrieve historical records for similar parts, to review accurately the status of all staff assignments, and to generate detailed machining procedures definitely can impact the way in which a machine shop prepared for new orders. The real payoff is in the hardcopy output (N/C programs, studies, sequence plans, and procedures). 4 figures,

A personal computer code for seismic evaluations of nuclear power plant facilities

International Nuclear Information System (INIS)

Xu, J.; Graves, H.

1990-01-01

A wide range of computer programs and modeling approaches are often used to justify the safety of nuclear power plants. It is often difficult to assess the validity and accuracy of the results submitted by various utilities without developing comparable computer solutions. Taken this into consideration, CARES is designed as an integrated computational system which can perform rapid evaluations of structural behavior and examine capability of nuclear power plant facilities, thus CARES may be used by the NRC to determine the validity and accuracy of analysis methodologies employed for structural safety evaluations of nuclear power plants. CARES has been designed to: operate on a PC, have user friendly input/output interface, and have quick turnaround. The CARES program is structured in a modular format. Each module performs a specific type of analysis. The basic modules of the system are associated with capabilities for static, seismic and nonlinear analyses. This paper describes the various features which have been implemented into the Seismic Module of CARES version 1.0. In Section 2 a description of the Seismic Module is provided. The methodologies and computational procedures thus far implemented into the Seismic Module are described in Section 3. Finally, a complete demonstration of the computational capability of CARES in a typical soil-structure interaction analysis is given in Section 4 and conclusions are presented in Section 5. 5 refs., 4 figs

Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1996-12-31

The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1997-12-31

The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

Plant Closings and Capital Flight: A Computer-Assisted Simulation.

Science.gov (United States)

Warner, Stanley; Breitbart, Myrna M.

1989-01-01

A course at Hampshire College was designed to simulate the decision-making environment in which constituencies in a medium-sized city would respond to the closing and relocation of a major corporate plant. The project, constructed as a role simulation with a computer component, is described. (MLW)

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...

Computer visualization for enhanced operator performance for advanced nuclear power plants

International Nuclear Information System (INIS)

Simon, B.H.; Raghavan, R.

1993-01-01

The operators of nuclear power plants are presented with an often uncoordinated and arbitrary array of displays and controls. Information is presented in different formats and on physically dissimilar instruments. In an accident situation, an operator must be very alert to quickly diagnose and respond to the state of the plant as represented by the control room displays. Improvements in display technology and increased automation have helped reduce operator burden; however, too much automation may lead to operator apathy and decreased efficiency. A proposed approach to the human-system interface uses modern graphics technology and advances in computational power to provide a visualization or ''virtual reality'' framework for the operator. This virtual reality comprises a simulated perception of another existence, complete with three-dimensional structures, backgrounds, and objects. By placing the operator in an environment that presents an integrated, graphical, and dynamic view of the plant, his attention is directly engaged. Through computer simulation, the operator can view plant equipment, read local displays, and manipulate controls as if he were in the local area. This process not only keeps an operator involved in plant operation and testing procedures, but also reduces personnel exposure. In addition, operator stress is reduced because, with realistic views of plant areas and equipment, the status of the plant can be accurately grasped without interpreting a large number of displays. Since a single operator can quickly ''visit'' many different plant areas without physically moving from the control room, these techniques are useful in reducing labor requirements for surveillance and maintenance activities. This concept requires a plant dynamic model continuously updated via real-time process monitoring. This model interacts with a three-dimensional, solid-model architectural configuration of the physical plant

Mesh influence on the fire computer modeling in nuclear power plants

Directory of Open Access Journals (Sweden)

D. Lázaro

2018-04-01

Full Text Available Fire computer models allow to study real fire scenarios consequences. Its use in nuclear power plants has increased with the new regulations to apply risk informed performance-based methods for the analysis and design of fire safety solutions. The selection of the cell side factor is very important in these kinds of models. The mesh must establish a compromise between the geometry adjustment, the resolution of the equations and the computation times. This paper aims to study the impact of several cell sizes, using the fire computer model FDS, to evaluate the relative affectation in the final simulation results. In order to validate that, we have employed several scenarios of interest for nuclear power plants. Conclusions offer relevant data for users and show some cell sizes that can be selected to guarantee the quality of the simulations and reduce the results uncertainty.

Bio-preparates support the productivity of potato plants grown under desert farming conditions of north Sinai: Five years of field trials

Directory of Open Access Journals (Sweden)

Mohammed T. Abbas

2014-01-01

Full Text Available Organic agriculture as well as good agricultural practices (GAPs intrigues the concern of both consumers and producers of agricultural commodities. Bio-preparates of various rhizospheric microorganisms (RMOs are potential sources of biological inputs supporting plant nutrition and health. The response of open-field potatoes to the application of RMO bio-preparates, the biofertilizer “Biofertile” and the bioagent “Biocontrol”, were experimented over 5 successive years under N-hunger of north Sinai desert soils. Both vegetative and tuber yields of a number of tested cultivars were significantly improved due to rhizobacterial treatments. In the majority of cases, the biofertilizer “Biofertile” did successfully supply ca. 50% of plant N requirements, as the yield of full N-fertilized plants was comparable to those received 50% N simultaneously with bio-preparates treatment. The magnitude of inoculation was cultivar-dependent; cvs. Valor and Oceania were among the most responsive ones. Bio-preparate introduction to the plant–soil system was successful via soaking of tubers and/or spraying the plant canopy. The “Biocontrol” formulation was supportive in controlling plant pathogens and significantly increased the fruit yields. The cumulative effect of both bio-preparates resulted in tuber yield increases of ca. 25% over control.

Some Aspects of Process Computers Configuration Control in Nuclear Power Plant Krsko - Process Computer Signal Configuration Database (PCSCDB)

International Nuclear Information System (INIS)

Mandic, D.; Kocnar, R.; Sucic, B.

2002-01-01

During the operation of NEK and other nuclear power plants it has been recognized that certain issues related to the usage of digital equipment and associated software in NPP technological process protection, control and monitoring, is not adequately addressed in the existing programs and procedures. The term and the process of Process Computers Configuration Control joins three 10CFR50 Appendix B quality requirements of Process Computers application in NPP: Design Control, Document Control and Identification and Control of Materials, Parts and Components. This paper describes Process Computer Signal Configuration Database (PCSCDB), that was developed and implemented in order to resolve some aspects of Process Computer Configuration Control related to the signals or database points that exist in the life cycle of different Process Computer Systems (PCS) in Nuclear Power Plant Krsko. PCSCDB is controlled, master database, related to the definition and description of the configurable database points associated with all Process Computer Systems in NEK. PCSCDB holds attributes related to the configuration of addressable and configurable real time database points and attributes related to the signal life cycle references and history data such as: Input/Output signals, Manually Input database points, Program constants, Setpoints, Calculated (by application program or SCADA calculation tools) database points, Control Flags (example: enable / disable certain program feature) Signal acquisition design references to the DCM (Document Control Module Application software for document control within Management Information System - MIS) and MECL (Master Equipment and Component List MIS Application software for identification and configuration control of plant equipment and components) Usage of particular database point in particular application software packages, and in the man-machine interface features (display mimics, printout reports, ...) Signals history (EEAR Engineering

Information technology impact on nuclear power plant documentation. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

International Nuclear Information System (INIS)

2002-04-01

As the majority of the nuclear power plants (NPPs) in the world were designed and constructed about twenty to forty years ago, these older power plants may have shortcomings in documentation on construction, commissioning, operations, maintenance, or decommissioning. Therefore, facility documentation does not always reflect actual plant status after years of plant operation, modification, and maintenance. To deal with these shortcomings, computer and information technologies that provide sophisticated and modern design tools as well as information processing and storage facilities can offer dramatic innovation from paper-centric documentation towards data-centric documentation. This report addresses all aspects of documentation associated with various life-cycle phases of NPPs and the information technology (IT) that are relevant to the documentation process. It also provides a guide for planning, designing, and executing an IT documentation project. Examples are given to demonstrate successful implementations at plants. Finally, it discusses the issues related to the application of the IT in NPPs and the trends for applications of the IT at NPPs as well as the technology itself. It is recognized that this can also improve configuration management. reliability of data, quality of personnel work, and ultimately plant performance reliability and safety. The aspects of using the IT for NPP documentation are closely related to configuration management at NPPs. The report consists of nine sections, a reference section, and five additional appendices. The development of this report which was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is the result of a series of consultants meetings held by the IAEA in Vienna (October 1999, November 2000). It was prepared with the participation and contributions of experts from Canada, Germany, Norway, Sweden, and the United States of America. In addition, a

Information technology impact on nuclear power plant documentation. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-04-01

As the majority of the nuclear power plants (NPPs) in the world were designed and constructed about twenty to forty years ago, these older power plants may have shortcomings in documentation on construction, commissioning, operations, maintenance, or decommissioning. Therefore, facility documentation does not always reflect actual plant status after years of plant operation, modification, and maintenance. To deal with these shortcomings, computer and information technologies that provide sophisticated and modern design tools as well as information processing and storage facilities can offer dramatic innovation from paper-centric documentation towards data-centric documentation. This report addresses all aspects of documentation associated with various life-cycle phases of NPPs and the information technology (IT) that are relevant to the documentation process. It also provides a guide for planning, designing, and executing an IT documentation project. Examples are given to demonstrate successful implementations at plants. Finally, it discusses the issues related to the application of the IT in NPPs and the trends for applications of the IT at NPPs as well as the technology itself. It is recognized that this can also improve configuration management. reliability of data, quality of personnel work, and ultimately plant performance reliability and safety. The aspects of using the IT for NPP documentation are closely related to configuration management at NPPs. The report consists of nine sections, a reference section, and five additional appendices. The development of this report which was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is the result of a series of consultants meetings held by the IAEA in Vienna (October 1999, November 2000). It was prepared with the participation and contributions of experts from Canada, Germany, Norway, Sweden, and the United States of America. In addition, a

Fruiting of browse plants affected by pine site preparation in east Texas

Science.gov (United States)

John J. Stransky; Douglas Richardson

1977-01-01

Pine planting sites prepared by burning yielded 120 kg/ha of browse fruits the third growing season after site treatment. Control plots yielded 74, KG-bladed plots 57, and chopped plots 41 kg/ha. Blackberries, American beautyberry, sumac, Sebastian bush, muscadine grape, blueberries, and southern wax-myrtle were the principal species. Most fruit was available in summer...

A survey of process control computers at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Dahl, C.A.

1989-01-01

The Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering Laboratory is charged with the safe processing of spent nuclear fuel elements for the United States Department of Energy. The ICPP was originally constructed in the late 1950s and used state-of-the-art technology for process control at that time. The state of process control instrumentation at the ICPP has steadily improved to keep pace with emerging technology. Today, the ICPP is a college of emerging computer technology in process control with some systems as simple as standalone measurement computers while others are state-of-the-art distributed control systems controlling the operations in an entire facility within the plant. The ICPP has made maximal use of process computer technology aimed at increasing surety, safety, and efficiency of the process operations. Many benefits have been derived from the use of the computers for minimal costs, including decreased misoperations in the facility, and more benefits are expected in the future

Hazard identification based on plant functional modelling

International Nuclear Information System (INIS)

Rasmussen, B.; Whetton, C.

1993-10-01

A major objective of the present work is to provide means for representing a process plant as a socio-technical system, so as to allow hazard identification at a high level. The method includes technical, human and organisational aspects and is intended to be used for plant level hazard identification so as to identify critical areas and the need for further analysis using existing methods. The first part of the method is the preparation of a plant functional model where a set of plant functions link together hardware, software, operations, work organisation and other safety related aspects of the plant. The basic principle of the functional modelling is that any aspect of the plant can be represented by an object (in the sense that this term is used in computer science) based upon an Intent (or goal); associated with each Intent are Methods, by which the Intent is realized, and Constraints, which limit the Intent. The Methods and Constraints can themselves be treated as objects and decomposed into lower-level Intents (hence the procedure is known as functional decomposition) so giving rise to a hierarchical, object-oriented structure. The plant level hazard identification is carried out on the plant functional model using the Concept Hazard Analysis method. In this, the user will be supported by checklists and keywords and the analysis is structured by pre-defined worksheets. The preparation of the plant functional model and the performance of the hazard identification can be carried out manually or with computer support. (au) (4 tabs., 10 ills., 7 refs.)

Effect of Preparation Depth on the Marginal and Internal Adaptation of Computer-aided Design/Computer-assisted Manufacture Endocrowns.

Science.gov (United States)

Gaintantzopoulou, M D; El-Damanhoury, H M

The aim of the study was to evaluate the effect of preparation depth and intraradicular extension on the marginal and internal adaptation of computer-aided design/computer-assisted manufacture (CAD/CAM) endocrown restorations. Standardized preparations were made in resin endodontic tooth models (Nissin Dental), with an intracoronal preparation depth of 2 mm (group H2), with extra 1- (group H3) or 2-mm (group H4) intraradicular extensions in the root canals (n=12). Vita Enamic polymer-infiltrated ceramic-network material endocrowns were fabricated using the CEREC AC CAD/CAM system and were seated on the prepared teeth. Specimens were evaluated by microtomography. Horizontal and vertical tomographic sections were recorded and reconstructed by using the CTSkan software (TView v1.1, Skyscan).The surface/void volume (S/V) in the region of interest was calculated. Marginal gap (MG), absolute marginal discrepancy (MD), and internal marginal gap were measured at various measuring locations and calculated in microscale (μm). Marginal and internal discrepancy data (μm) were analyzed with nonparametric Kruskal-Wallis analysis of variance by ranks with Dunn's post hoc, whereas S/V data were analyzed by one-way analysis of variance and Bonferroni multiple comparisons (α=0.05). Significant differences were found in MG, MD, and internal gap width values between the groups, with H2 showing the lowest values from all groups. S/V calculations presented significant differences between H2 and the other two groups (H3 and H4) tested, with H2 again showing the lowest values. Increasing the intraradicular extension of endocrown restorations increased the marginal and internal gap of endocrown restorations.

PCTRAN-3: The third generation of personal computer-based plant analyzer for severe accident management

International Nuclear Information System (INIS)

Li-Chi Cliff Po; Link, John M.

2004-01-01

PCTRAN is a plant analyzer that uses a personal computer to simulate plant response. The plant model is recently expanded to accommodate beyond design-basis severe accidents. In the event of multiple failures of the plant safety systems, the core may experience heatup and extensive failure. Using a high-powered personal computer (PC), PCTRAN-3 is designed to operate at a speed significantly faster than real-time. A convenient, interactive and user-friendly graphics interface allows full control by the operator. The plant analyzer is intended for use in severe accident management. In this paper the code's component models and sample runs ranging from normal operational transients to severe accidents are reviewed. (author)

Problems in modernization of automation systems at coal preparation plants

Science.gov (United States)

Myshlyaev, L. P.; Lyakhovets, M. V.; Venger, K. G.; Leontiev, I. A.; Makarov, G. V.; Salamatin, A. S.

2018-05-01

The factors influencing the process of modernization (reconstruction) of the automation systems at coal preparation plants are described. Problems such as heterogeneity of existing and developed systems, planning of reconstruction of a technological complex without taking into account modernization of automated systems, commissioning without stopping the existing technological complex, as well as problems of conducting procurement procedures are discussed. The option of stage-by-stage start-up and adjustment works in the conditions of modernization of systems without long stops of the process equipment is offered.

Metal nanoparticles (other than gold or silver) prepared using plant extracts for medical applications

Science.gov (United States)

Pasca, Roxana-Diana; Santa, Szabolcs; Racz, Levente Zsolt; Racz, Csaba Pal

2016-12-01

There are many modalities to prepare metal nanoparticles, but the reducing of the metal ions with plant extracts is one of the most promising because it is considerate less toxic for the environment, suitable for the use of those nanoparticles in vivo and not very expensive. Various metal ions have been already studied such as: cobalt, copper, iron, platinum, palladium, zinc, indium, manganese and mercury and the number of plant extracts used is continuously increasing. The prepared systems were characterized afterwards with a great number of methods of investigation: both spectroscopic (especially UV-Vis spectroscopy) and microscopic (in principal, electron microscopy-TEM) methods. The applications of the metal nanoparticles obtained are diverse and not completely known, but the medical applications of such nanoparticles occupy a central place, due to their nontoxic components, but some diverse industrial applications do not have to be forgotten.

Effects of Mechanical Site Preparation on Growth of Oaks Planted on Former Agricultural Fields

Directory of Open Access Journals (Sweden)

John D. Hodges

2011-12-01

Full Text Available Mechanical site preparation is frequently proposed to alleviate problematic soil conditions when afforesting retired agricultural fields. Without management of soil problems, any seedlings planted in these areas may exhibit poor growth and survival. While mechanical site preparation methods currently employed in hardwood afforestation are proven, there is a substantial void in research comparing subsoiling, bedding, and combination plowing treatments. A total of 4,320 bare-root Nuttall oak (Quercus texana Buckley, Shumard oak (Quercus shumardii Buckley, and swamp chestnut oak (Quercus michauxii Nutt. seedlings were planted in February 2008 on three Mississippi sites. All sites were of comparable soils and received above average precipitation throughout the three-year duration of the study. Four site preparation treatments were replicated at each site, with 480 seedlings planted in each of nine replications, and a total of 1,440 seedlings per species planted across all sites. Mechanical treatments were installed using 3.1 m row centers, with treatments as follows: control, subsoiling, bedding, and combination plowing. Treatment effects on seedling height, groundline diameter (GLD, and survival were analyzed. Seedlings exhibited greater height in bedded and combination plowed areas (79.7 cm to 102.7 cm and 82.6 cm to 100.1 cm, respectively compared to subsoiled or control areas (70.4 cm to 84.6 cm and 71.4 cm to 86.9 cm, respectively. Greater GLD was observed in bedded and combination plowed areas (11.9 mm to 18.4 mm and 12.2 mm to 18.3 mm, respectively compared to subsoiled or control areas (10.2 mm to 14.6 mm and 10.5 mm to 15.6 mm, respectively. Survival was high for this study (94.%, and no differences were detected among treatments.

Standard assays do not predict the efficiency of commercial cellulase preparations towards plant materials

NARCIS (Netherlands)

Kabel, M.A.; Maarel, van der M.J.E.C.; Klip, G.; Voragen, A.G.J.; Schols, H.A.

2006-01-01

Commercial cellulase preparations are potentially effective for processing biomass feedstocks in order to obtain bioethanol. In plant cell walls, cellulose fibrils occur in close association with xylans (monocotyls) or xyloglucans (dicotyls). The enzymatic conversion of cellulose/xylans is a complex

Standard Assays Do Not Predict the Efficiency of Commercial Cellulase Preparations Towards Plant Materials

NARCIS (Netherlands)

Kabel, Mirjam A.; Maarel, Marc J.E.C. van der; Klip, Gert; Voragen, Alphons G.J.; Schols, Henk A.

2006-01-01

Commercial cellulase preparations are potentially effective for processing biomass feedstocks in order to obtain bioethanol. In plant cell walls, cellulose fibrils occur in close association with xylans (monocotyls) or xyloglucans (dicotyls). The enzymatic conversion of cellulose/xylans is a complex

Computer simulation of nuclear pollutant diffusion from Shimane nuclear power plants and development of an evacuation strategy in the event of a nuclear incident

International Nuclear Information System (INIS)

Yakura, Haruna; Kurimasa, Akihiro

2012-01-01

Beginning from Tohoku (northeastern) Earthquake on March 11, an accident at the Fukushima Dai-ichi Nuclear Power Plant resulted in a substantial release of radioactivity to the environment. The accident forced a large number of residents to evacuate from surrounding areas. Moreover, the nuclear incident was life-threatening for the elderly and for people with serious illnesses who were confined in hospital or nursing homes. Strikingly, the causes of death were not directly attributed to radiation exposure but to problems encountered during evacuation. Using nuclear diffusion data from the Fukushima incident, we simulated nuclear pollutant dispersion using computer software A2C in an area of Tottori and Shimane Prefectures surrounding the Shimane Nuclear Power Plant. We generated a model for the spread of nuclear pollutants around the Emergency Planning Zone, id est (i.e.) EPZ. From these findings, we proposed evacuation strategies for residents near the power plant to ensure a safe and reliable escape from nuclear pollutants. Our recommendations include: immediate evacuation from PAZ area (within 5 km), securing indoor shelter in the area of the UPZ (from 5 km to 30 km) and preparations to evacuate further outwards from the nuclear plant site, daytime evacuation within a 30 km area after considering wind direction and velocity, and preparation of a planned evacuation strategy that identifies secure facilities for weaker people in the event of a disaster. (author)

Applying computer-based procedures in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Mauro V. de; Carvalho, Paulo V.R. de; Santos, Isaac J.A.L. dos; Grecco, Claudio H.S. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Instrumentacao e Confiabilidade Humana], e-mail: mvitor@ien.gov.br, e-mail: paulov@ien.gov.br, e-mail: luquetti@ien.gov.br, e-mail: grecco@ien.gov.br; Bruno, Diego S. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Escola Politecnica. Curso de Engenharia de Controle e Automacao], e-mail: diegosalomonebruno@gmail.com

2009-07-01

Plant operation procedures are used to guide operators in coping with normal, abnormal or emergency situations in a process control system. Historically, the plant procedures have been paper-based (PBP), with the digitalisation trend in these complex systems computer-based procedures (CBPs) are being developed to support procedure use. This work shows briefly the research on CBPs at the Human-System Interface Laboratory (LABIHS). The emergency operation procedure EOP-0 of the LABIHS NPP simulator was implemented in the ImPRO CBP system. The ImPRO system was chosen for test because it is available for download in the Internet. A preliminary operation test using the implemented procedure in the CBP system was realized and the results were compared to the operation through PBP use. (author)

Computer program for afterheat temperature distribution for mobile nuclear power plant

Science.gov (United States)

Parker, W. G.; Vanbibber, L. E.

1972-01-01

ESATA computer program was developed to analyze thermal safety aspects of post-impacted mobile nuclear power plants. Program is written in FORTRAN 4 and designed for IBM 7094/7044 direct coupled system.

Software and man-machine interface considerations for a nuclear plant computer replacement and upgrade project

International Nuclear Information System (INIS)

Diamond, G.; Robinson, E.

1984-01-01

Some of the key software functions and Man-Machine Interface considerations in a computer replacement and upgrade project for a nuclear power plant are described. The project involves the installation of two separate computer systems: an Emergency Response Facilities Computer System (ERFCS) and a Plant Process Computer System (PPCS). These systems employ state-of-the-art computer hardware and software. The ERFCS is a new system intended to provide enhanced functions to meet NRC post-TMI guidelines. The PPCS is intended to replace and upgrade an existing obsolete plant computer system. A general overview of the hardware and software aspects of the replacement and upgrade is presented. The work done to develop the upgraded Man-Machine Interface is described. For the ERFCS, a detailed discussion is presented of the work done to develop logic to evaluate the readiness and performance of safety systems and their supporting functions. The Man-Machine Interface considerations of reporting readiness and performance to the operator are discussed. Finally, the considerations involved in the implementation of this logic in real-time software are discussed.. For the PPCS, a detailed discussion is presented of some new features

Computer handling of Savannah River Plant environmental monitoring data

International Nuclear Information System (INIS)

Zeigler, C.C.

1975-12-01

At the Savannah River Plant, computer programs are used to calculate, store, and retrieve radioactive and nonradioactive environmental monitoring data. Objectives are to provide daily, monthly, and annual summaries of all routine monitoring data; to calculate and tabulate releases according to radioisotopic species or nonradioactive pollutant, source point, and mode of entry to the environment (atmosphere, stream, or earthen seepage basins). The computer programs use a compatible numeric coding system for the data, and printouts are in the form required for internal and external reports. Data input and program maintenance are accomplished with punched cards, paper or magnetic tapes, and when applicable, with computer terminals. Additional aids for data evaluation provided by the programs are statistical counting errors, maximum and minimum values, standard deviations of averages, and other statistical analyses

Effect of biological and chemical preparations on peroxidase activity in leaves of tomato plants

Directory of Open Access Journals (Sweden)

Yulia Kolomiets

2016-10-01

Full Text Available In terms of treating tomato variety Chaika with chemical preparations with active substances if aluminum phosphate, 570 g/l + phosphorous acid 80 g/,l and mankotseb in concentration of 640 g/kg, the maximum increase in peroxidase activity in leaves of plants was observed in12 hours. In terms of use of biological preparations based on living cells Bacillus subtilis and Azotobacter chroococcum its activity was maximum in 24 hours and ranged from 77.7 to 112.7 un.mg-1•s-1

Improving of the water preparation systems in the industry thermal power plants

Directory of Open Access Journals (Sweden)

Choshnova Daniela

2018-01-01

Full Text Available Some modern possibilities for modernization of the water preparation in the heat power plants of metallurgical enterprises are presented. It is focused on the ecological and technological advantages of the methods for obtaining of ultra-pure water. This work is not intended to justify the need of usage of particular technology in an object. This is a separate task requiring in-depth consideration.

Information integration in control rooms and technical offices in nuclear power plants. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

International Nuclear Information System (INIS)

2001-11-01

The majority of the nuclear power plants in the world were designed 25 to 45 years ago. The information, instrumentation, safety, and control systems in these plant designs were based on analog, relay, and primitive digital technology. Computers that were available when most of the nuclear power plants were built were unsophisticated compared with those currently available. These less powerful machines with limited computational capabilities and memory were used to collect and store information. The main means for obtaining information from the plant were analog meters and strip chart recorders. In many cases these pieces of data had to be integrated and correlated with other data manually, in order to be usable. Procedures and plant information resided on paper only and were frequently hard to find and access in a timely manner. This report provides guidance to help with the integration of information in order to enhance the usability and usefulness of the information. It can also be used to help avoid the pitfalls that can occur when implementing new systems with respect to the information they need and produce. This reports philosophy is based on three important issues that allow the convenient structuring of the problem and to keep all of its important features. The first issue is the process of information systems integration and use. This is achieved by long term planning and the creation of the plant infrastructure plan. The second is to take care of the end users' needs in relation to their abilities. This is realized through analyses of user needs. Third is the design of the human-system interface (HSI), for example to distinguish between types of information for use in the plant control room and in technical offices. The development of this report was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is a logical follow-up to IAEA-TECDOC-1016, Modernization of Instrumentation and Control

CEGB philosophy and experience with fault-tolerant micro-computer application for power plant controls

International Nuclear Information System (INIS)

Clinch, D.A.L.

1986-01-01

From the mid-1960s until the late 1970s, automatic modulating control of the main boiler plant on CEGB fossil-fired power stations was largely implemented with hard wired electronic equipment. Mid-way through this period, the CEGB formulated a set of design requirements for this type of equipment; these laid particular emphasis on the fault tolerance of a control system and specified the nature of the interfaces with a control desk and with plant regulators. However, the automatic control of an Advanced Gas Cooled Reactor (AGR) is based upon measured values which are derived by processing a large number of thermocouple signals. This is more readily implemented digitally than with hard-wired equipment. Essential to the operation of an AGR power station is a data processing (DP) computer for monitoring the plant; so the first group of AGR power stations, designed in the 1960s, employed their DP computers for modulating control. Since the late 1970s, automatic modulating control of major plants, for new power stations and for re-fits on established power stations, has been implemented with micro-computers. Wherever practicable, the policy formulated earlier for hard-wired equipment has been retained, particularly in respect of the interfaces. This policy forms the foundation of the fault tolerance of these micro-computer systems

Cyber Security on Nuclear Power Plant's Computer Systems

Energy Technology Data Exchange (ETDEWEB)

Shin, Ick Hyun [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2010-10-15

Computer systems are used in many different fields of industry. Most of us are taking great advantages from the computer systems. Because of the effectiveness and great performance of computer system, we are getting so dependable on the computer. But the more we are dependable on the computer system, the more the risk we will face when the computer system is unavailable or inaccessible or uncontrollable. There are SCADA, Supervisory Control And Data Acquisition, system which are broadly used for critical infrastructure such as transportation, electricity, water management. And if the SCADA system is vulnerable to the cyber attack, it is going to be nation's big disaster. Especially if nuclear power plant's main control systems are attacked by cyber terrorists, the results may be huge. Leaking of radioactive material will be the terrorist's main purpose without using physical forces. In this paper, different types of cyber attacks are described, and a possible structure of NPP's computer network system is presented. And the paper also provides possible ways of destruction of the NPP's computer system along with some suggestions for the protection against cyber attacks

Use of new ceramic linings in coal preparation plants

Energy Technology Data Exchange (ETDEWEB)

Fedorchenko, V.E.; Rudenko, V.A.; Bondarev, A.Ya.

1984-01-01

This article evaluates several materials used as liners in coal preparation equipment. The evaluations concentrate on liners used under conditions of intensive temperature fluctuations, e.g. liners of coal chutes for coal transport from coal dryers. Two aspects of wear are analyzed: abrasion by friction and effects of temperature fluctuations. Abrasive wear is tested using magnetite suspension with a density of 400 g/l. Tests show that abrasive wear of liners on an alumina basis is 3 times lower than abrasive wear of high quality steel, from 13 to 24 times lower than that of iron and from 6 to 8 times lower than that of steels used in coal preparation plants. Effects of temperature fluctuations from 20 to 840 C on abrasive wear of liners of steels, iron, slag glass ceramics, mullite-corundum material and corundum is shown in a table. The test show that mullite-corundum material on the basis of alumina is characterized by a high resistance to abrasive wear after 30 cycles of temperature increase from 20 to 840 C and decrease to 20 C. Using mullite-corundum as liners of equipment and installations operating under conditions of temperature fluctuations is recommended.

ESP and NOAH: computer programs for flood-risk analysis of nuclear power plants

International Nuclear Information System (INIS)

Wagner, D.P.; Montague, D.F.; Rooney, J.J.; Fussell, J.B.; Baker, L.S.

1982-06-01

This report describes a computer program package that aids in assessing the impact of floods on risk from nuclear power plants. The package consists of two distinct computer programs: ESP and NOAH. The ESP program improves the efficiency of a flood analysis by screening accident sequences and identifying accident sequences that are potentially significant contributors to risk in the event of a flood. Input to ESP includes accident sequences from an existing risk assessment and flood screening criteria. The NOAH program provides detailed qualitative analysis of the plant systems identified by ESP. NOAH performs a qualitative flood simulation of the fault tree

Simple preparation of plant epidermal tissue for laser microdissection and downstream quantitative proteome and carbohydrate analysis

Directory of Open Access Journals (Sweden)

Christian eFalter

2015-03-01

Full Text Available The outwardly directed cell wall and associated plasma membrane of epidermal cells represent the first layers of plant defense against intruding pathogens. Cell wall modifications and the formation of defense structures at sites of attempted pathogen penetration are decisive for plant defense. A precise isolation of these stress-induced structures would allow a specific analysis of regulatory mechanism and cell wall adaption. However, methods for large-scale epidermal tissue preparation from the model plant Arabidopsis thaliana, which would allow proteome and cell wall analysis of complete, laser-microdissected epidermal defense structures, have not been provided. We developed the adhesive tape – liquid cover glass technique for simple leaf epidermis preparation from A. thaliana, which is also applicable on grass leaves. This method is compatible with subsequent staining techniques to visualize stress-related cell wall structures, which were precisely isolated from the epidermal tissue layer by laser microdissection coupled to laser pressure catapulting. We successfully demonstrated that these specific epidermal tissue samples could be used for quantitative downstream proteome and cell wall analysis. The development of the adhesive tape – liquid cover glass technique for simple leaf epidermis preparation and the compatibility to laser microdissection and downstream quantitative analysis opens new possibilities in the precise examination of stress- and pathogen-related cell wall structures in epidermal cells. Because the developed tissue processing is also applicable on A. thaliana, well-established, model pathosystems that include the interaction with powdery mildews can be studied to determine principal regulatory mechanisms in plant-microbe interaction with their potential outreach into crop breeding.

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

International Nuclear Information System (INIS)

1994-06-01

This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs.

Improvement of nuclear power plant monitor and control equipment. Computer application backfitting

International Nuclear Information System (INIS)

Hayakawa, H.; Kawamura, A.; Suto, O.; Kinoshita, Y.; Toda, Y.

1985-01-01

This paper describes the application of advanced computer technology to existing Japanese Boiling Water Reactor (BWR) nuclear power plants for backfitting. First we review the background of the backfitting and the objectives of backfitting. A feature of backfitting such as restrictions and constraints imposed by the existing equipment are discussed and how to overcome these restrictions by introduction of new technology such as highly efficient data transmission using multiplexing, and compact space saving computer systems are described. Role of the computer system in reliable NPS are described with a wide spectrum of TOSHIBA backfitting computer system application experiences. (author)

The computer code system for reactor radiation shielding in design of nuclear power plant

International Nuclear Information System (INIS)

Li Chunhuai; Fu Shouxin; Liu Guilian

1995-01-01

The computer code system used in reactor radiation shielding design of nuclear power plant includes the source term codes, discrete ordinate transport codes, Monte Carlo and Albedo Monte Carlo codes, kernel integration codes, optimization code, temperature field code, skyshine code, coupling calculation codes and some processing codes for data libraries. This computer code system has more satisfactory variety of codes and complete sets of data library. It is widely used in reactor radiation shielding design and safety analysis of nuclear power plant and other nuclear facilities

Basic user guide for the radwaste treatment plant computer system

International Nuclear Information System (INIS)

Keel, A.

1990-07-01

This guide has been produced as an aid to using the Radwaste Treatment Plant computer system. It is designed to help new users to use the database menu system. Some of the forms can be used in ways different from those explained and more complex queries can be performed. (UK)

Application of process computers and colour CRT displays in the plant control room of a BWR

International Nuclear Information System (INIS)

Itoh, M.; Hayakawa, H.; Kawahara, H.; Neda, T.; Wakabayashi, Y.

1983-01-01

The recent application of a CRT display system in an 1100-MW(e) BWR plant control room and the design features of a new control room whose installation is planned for the next generation are discussed. As reactor unit capacity and the need for plant safety and reliability continue to increase, instrumentation and control equipment is growing in number and complexity. In consequence, control and supervision of plant operations require improvement. Thus, because of recent progress in the field of process computers and display equipment (colour CRTs), efficient improvements of the control room are under way in the Japanese BWR plant. In the recently constructed BWR plant (1100 MW(e)), five CRTs on the bench board and two process computers were additionally installed in the control room during the construction stage to improve plant control and supervisory functions by implementing the lessons learned from the Three Mile Island incident. The major functions of the new computers and display systems are to show integrated graphic displays of the plant status, to monitor the standby condition of the safety system, to show the condition of the integrated alarm system, etc. In practice, in the actual plant, this newly installed system performs well. On the basis of the experience gained in these activities, a new computerized control and monitoring system is now being designed for subsequent domestic BWR plants. This advanced system will incorporate not only the functions already mentioned, but also a surveillance guide system and plant automation. For future plants, a diagnostic system and an instructional system that can analyse a disturbance and give operational guidance to the plant operator are being developed in a government-sponsored programme. (author)

Use of ETOG and ETOT computer codes for preparating the Library of LEOPARD with data from ENDFIB-IV

International Nuclear Information System (INIS)

Cunha Menezes Filho, A. da.

1983-01-01

The modifications carried out in the ETOT-3 and ETOG-3 computer codes used for preparating the thermal (172 energy groups) and epithermal (54 energy groups) libraries, respectivelly, of LEOPARD computer code, are presented. (M.C.K.) [pt

Computer aided design of piping for a radiochemical plant

Energy Technology Data Exchange (ETDEWEB)

Selvaraj, P G; Chandrasekhar, A; Chandrasekar, A V [Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Raju, R P; Mahudeeswaran, K V; Kumar, S V [Reprocessing Group, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

In a radiochemical plant such as reprocessing plants, process equipment, storage tanks, liquid transfer systems and the associated pipe lines etc. are housed in series of concrete cells. Availability of limited cell space/volume, provision of various modes of liquid transfers with associated redundancies and instrumentation lines with standby alternatives increase the overall piping density. Designing such high density piping layout without interference is quite complex and needs lot of human efforts. This paper briefly describes development of computer codes for the entire scheme of design, drafting and fabrication of piping for nuclear fuel reprocessing plant. The general organisation of various programs, their functions, the complete sequence of the scheme and the flow of data are presented. High degree of reliability of each routine, considerable error checking facilities, marking legends on the drawings, provision for scaling in drafting and accuracy to the extent of one mm in layout design are some of the important features of this scheme. (author). 1 fig.

Information flow a data bank preparation in nuclear power plant reliability information system

International Nuclear Information System (INIS)

Kolesa, K.; Vejvodova, I.

1983-01-01

In the year 1981 the reliability information system for nuclear power plants (ISS-JE) was established. The objective of the system is to make a statistical evaluation of the operation of nuclear power plants and to obtain information on the reliability of the equipment of nuclear power plants and the transmission of this information to manufacturers with the aim of inducing them to take corrective measures. The HP 1000 computer with the data base system IMAGE 100 is used which allows to process single queries and periodical outputs. The content of periodical outputs designed for various groups of subcontractors is briefly described and trends of the further development of the system indicated. (Ha)

The first accident simulation of Angra-1 power plant using the ALMOD computer code

International Nuclear Information System (INIS)

Camargo, C.T.M.

1981-01-01

The implementation of the german computer code ALMOD and its application in the calculation of Angra-1, a nuclear power plant different from the KWU power plants, demanded study and models adaptation, and due to economic reasons simplifications and optimizations were necessary. The first results define the analytical potential of the computer code, confirm the adequacy of the adaptations done and provide relevant conclusions about the Angra-1 safety analysis, showing at the same time areas in which the model can be applied or simply improved. (E.G.) [pt

Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

International Nuclear Information System (INIS)

Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

1978-10-01

The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

Joint verification project on environmentally friendly coal utilization systems. Joint verification project on the water-saving coal preparation system; Kankyo chowagata sekitan riyo system kyodo jissho jigyo. Shosuigata sentan system kyodo jissho jigyo

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

In this verification project, clean technology which should be spread in China was verified and the base structure for its spread was prepared for the purpose of controlling emissions of environmental pollutants associated with the coal utilization in China and of contributing to secure energy acquisition of Japan. As joint verification projects, a general rehabilitation type coal preparation system was installed in the Wangfenggang coal preparation plant, and a central control coal preparation system was installed in the Qingtan coal preparation plant. In the former, a system is verified in which optimum operation, water-saving, high quality, and heightening of efficiency can be obtained by introducing two computing systems for operation control and quality control, various measuring instruments, and analyzers to coal preparation plants where analog operation is conducted helped by Russia and Porland and have problems about quality control. In the latter, a central control system achieving water saving is verified by introducing rapid ash meters, scales, desitometers and computers to coal preparation plants having zigzag or heavy-fluid cyclon and connecting various kinds of information through network. For fiscal 1994, investigation and study were conducted. 51 figs., 9 tabs.

Application of ESER computers to operation management of nuclear power plants

International Nuclear Information System (INIS)

Kuhne, E.; Poetter, K.F.; Suschok, G.

1990-01-01

Operation management of nuclear reactors is essentially support by calculational studies in which large computers have to be employed. A system of programs is presented that support the solution of those tasks which are related to refuelling and stationary operation of WWER-440 type reactors. Application of this system is made in the Greifswald nuclear power plant 'Bruno Leuschner' using access to the ESER computers at the Neubrandenburg Data Processing Centre in the teleprocessing mode. System solution and hardware used are described. (author)

Modernization of the automation control system of technological processes at the preparation plant in the conditions of technical re-equipment

Science.gov (United States)

Lyakhovets, M. V.; Wenger, K. G.; Myshlyaev, L. P.; Shipunov, M. V.; Grachev, V. V.; Melkozerov, M. Yu; Fairoshin, Sh A.

2018-05-01

The experience of modernization of the automation control system of technological processes at the preparation plant under the conditions of technical re-equipment of the preparation plant “Barzasskoye Tovarischestvo” LLC (Berezovsky) is considered. The automated process control systems (APCS), the modernization goals and the ways to achieve them are indicated, the main subsystems of the integrated APCS are presented, the enlarged functional and technical structure of the upgraded system is given. The procedure for commissioning an upgraded system is described.

Concept of a computer network architecture for complete automation of nuclear power plants

International Nuclear Information System (INIS)

Edwards, R.M.; Ray, A.

1990-01-01

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

Programmable logic control applied to a coal preparation plant complex

Energy Technology Data Exchange (ETDEWEB)

Krahenbil, L W

1979-02-01

The programmable Logic Controller (PLC), at its present stage of evolution, is now considered as a mature control system. The PLC combines the solid-state reliability of hard-wired logic and computer control systems with the simplicity of a relay ladder logic. Relay symbolic programming through a function-oriented keyboard provides a means which plant personnel can easily become accoustomed to work with. In a large coal facility, it is shown that the control engineer can provide improved control flexibility with the advanced capabilities of the PLC.

Operational experience with the Sizewell B integrated plant computer system

International Nuclear Information System (INIS)

Ladner, J.E.J.; Alexander, N.C.; Fitzpatrick, J.A.

1997-01-01

The Westinghouse Integrated System for Centralised Operation (WISCO) is the primary plant control system at the Sizewell B Power Station. It comprises three subsystems; the High Integrity Control System (HICS), the Process Control System (PCS) and the Distributed Computer system (DCS). The HICS performs the control and data acquisition of nuclear safety significant plant systems. The PCS uses redundant data processing unit pairs. The workstations and servers of the DCS communicate with each other over a standard ethernet. The maintenance requirements for every plant system are covered by a Maintenance Strategy Report. The breakdown of these reports is listed. The WISCO system has performed exceptionally well. Due to the diagnostic information presented by the HICS, problems could normally be resolved within 24 hours. There have been some 200 outstanding modifications to the system. The procedure of modification is briefly described. (A.K.)

Computations of steam flow and heat transfer in nuclear power plant condensers

International Nuclear Information System (INIS)

Yuan, A.

1997-01-01

To improve performance of its PWR nuclear power plants, Electricite de France has developed a performance monitoring system that checks simultaneously the operation of the components of the secondary system. The performance monitoring system is based on a computational software CITER for steady state runs. A one-dimensional condenser model has been developed. Application of this code to a nuclear power plant condenser shows that predicted values in good agreement with the design values

Computer functions in overall plant control of candu generating stations

International Nuclear Information System (INIS)

Chou, Q.B.; Stokes, H.W.

1976-01-01

System Planning Specifications form the basic requirements for the performance of the plant including its response to abnormal situations. The rules for the computer control programs are devised from these, taking into account limitations imposed by the reactor, heat transport and turbine-generator systems. The paper outlines these specifications and the limitations imposed by the major items of plant equipment. It describes the functions of each of the main programs, their interactions and the control modes used in the existing Ontario Hydro's nuclear station or proposed for future stations. Some simulation results showing the performance of the overall unit control system and plans for future studies are discussed. (orig.) [de

Thermohydraulic analysis of nuclear power plant accidents by computer codes

International Nuclear Information System (INIS)

Petelin, S.; Stritar, A.; Istenic, R.; Gregoric, M.; Jerele, A.; Mavko, B.

1982-01-01

RELAP4/MOD6, BRUCH-D-06, CONTEMPT-LT-28, RELAP5/MOD1 and COBRA-4-1 codes were successful y implemented at the CYBER 172 computer in Ljubljana. Input models of NPP Krsko for the first three codes were prepared. Because of the high computer cost only one analysis of double ended guillotine break of the cold leg of NPP Krsko by RELAP4 code has been done. BRUCH code is easier and cheaper for use. Several analysis have been done. Sensitivity study was performed with CONTEMPT-LT-28 for double ended pump suction break. These codes are intended to be used as a basis for independent safety analyses. (author)

Computational model for the tritium inventory management in a nuclear plant

International Nuclear Information System (INIS)

Zamfirache, M.; Bornea, A.; Stefanescu, I.; Stefan, L.; Bidica, N.; Vasut, F.; David, C.

2010-01-01

Full text: ICIT Rm. Valcea has built an experimental pilot plant having as the main objective the development of a technology for detritiation of heavy water processed in CANDU-type reactors at the nuclear power plant in Cernavoda, Romania. The aspects related to safeguards and safety for such a detritiation installation being of great importance, a complex computational model has been developed. The model allows real-time calculation of tritium inventory in a working installation. The applied detritiation technology is catalyzed isotopic exchange coupled with cryogenic distillation. The computational model was developed as based on the experience obtained in the pilot installation operation. The model uses a set of coefficients specific for isotopic exchange processes. The coefficients were experimentally determined in the pilot installation. The model is included in the monitoring system and uses as input data the parameters acquired in real-time from automation system of the pilot installation. A friendly interface has been created to visualize the final results as data or graphs. (authors)

ENEL overall PWR plant models and neutronic integrated computing systems

International Nuclear Information System (INIS)

Pedroni, G.; Pollachini, L.; Vimercati, G.; Cori, R.; Pretolani, F.; Spelta, S.

1987-01-01

To support the design activity of the Italian nuclear energy program for the construction of pressurized water reactors, the Italian Electricity Board (ENEL) needs to verify the design as a whole (that is, the nuclear steam supply system and balance of plant) both in steady-state operation and in transient. The ENEL has therefore developed two computer models to analyze both operational and incidental transients. The models, named STRIP and SFINCS, perform the analysis of the nuclear as well as the conventional part of the plant (the control system being properly taken into account). The STRIP model has been developed by means of the French (Electricite de France) modular code SICLE, while SFINCS is based on the Italian (ENEL) modular code LEGO. STRIP validation was performed with respect to Fessenheim French power plant experimental data. Two significant transients were chosen: load step and total load rejection. SFINCS validation was performed with respect to Saint-Laurent French power plant experimental data and also by comparing the SFINCS-STRIP responses

Computer techniques for experimental work in GDR nuclear power plants with WWER

International Nuclear Information System (INIS)

Stemmler, G.

1985-01-01

Nuclear power plant units with WWER are being increasingly equipped with high-performance, programmable process control computers. There are, however, essential reasons for further advancing the development of computer-aided measuring systems, in particular for experimental work. A special structure of such systems, which is based on the division into relatively rigid data registration and primary handling and into further processing by advanced programming language, has proved useful in the GDR. (author)

Computation and experiment results of the grounding model of Three Gorges Power Plant

Energy Technology Data Exchange (ETDEWEB)

Wen Xishan; Zhang Yuanfang; Yu Jianhui; Chen Cixuan [Wuhan University of Hydraulic and Electrical Engineering (China); Qin Liming; Xu Jun; Shu Lianfu [Yangtze River Water Resources Commission, Wuhan (China)

1999-07-01

A model for the computation of the grounding parameters of the grids of Three Gorges Power Plant (TGPP) on the Yangtze River is presented in this paper. Using this model computation and analysis of grounding grids is carried out. The results show that reinforcing the grid of the dam is the main body of current dissipation. It must be reliably welded to form a good grounding grid. The experimental results show that the method and program of the computations are correct. (UK)

Modernization of computer of plant Vandellos-II; Modernizacion del ordenador de planta de Vandello-II

Energy Technology Data Exchange (ETDEWEB)

Fuente Arias, E. de la

2014-07-01

The Plant computer from the nuclear de Vandellos II, whose modernization process will carry out Westinghouse, is a centralized system which performs monitoring and supervision in real time of plant processes and which performs the calculations necessary for an efficient assessment of plant operation, without performing any action on it. Its main function is to provide current and historical information on the status of the plant, both in normal operation and emergency conditions. (Author)

A personal computer code for seismic evaluations of nuclear power plants facilities

International Nuclear Information System (INIS)

Xu, J.; Philippacopoulos, A.J.; Graves, H.

1990-01-01

The program CARES (Computer Analysis for Rapid Evaluation of Structures) is an integrated computational system being developed by Brookhaven National Laboratory (BNL) for the U.S. Nuclear Regulatory Commission. It is specifically designed to be a personal computer (PC) operated package which may be used to determine the validity and accuracy of analysis methodologies used for structural safety evaluations of nuclear power plants. CARES is structured in a modular format. Each module performs a specific type of analysis i.e., static or dynamic, linear or nonlinear, etc. This paper describes the various features which have been implemented into the Seismic Module of CARES

Process description and plant design for preparing ceramic high-level waste forms

International Nuclear Information System (INIS)

Grantham, L.F.; McKisson, R.L.; Guon, J.; Flintoff, J.F.; McKenzie, D.E.

1983-01-01

The ceramics process flow diagram has been simplified and upgraded to utilize only two major processing steps - fluid-bed calcination and hot isostatic press consolidating. Full-scale fluid-bed calcination has been used at INEL to calcine high-level waste for 18 y; and a second-generation calciner, a fully remotely operated and maintained calciner that meets ALARA guidelines, started calcining high-level waste in 1982. Full-scale hot isostatic consolidation has been used by DOE and commercial enterprises to consolidate radioactive components and to encapsulate spent fuel elements for several years. With further development aimed at process integration and parametric optimization, the operating knowledge of full-scale demonstration of the key process steps should be rapidly adaptable to scale-up of the ceramic process to full plant size. Process flowsheets used to prepare ceramic and glass waste forms from defense and commercial high-level liquid waste are described. Preliminary layouts of process flow diagrams in a high-level processing canyon were prepared and used to estimate the preliminary cost of the plant to fabricate both waste forms. The estimated costs for using both options were compared for total waste management costs of SRP high-level liquid waste. Using our design, for both the ceramic and glass plant, capital and operating costs are essentially the same for both defense and commercial wastes, but total waste management costs are calculated to be significantly less for defense wastes using the ceramic option. It is concluded from this and other studies that the ceramic form may offer important advantages over glass in leach resistance, waste loading, density, and process flexibility. Preliminary economic calculations indicate that ceramics must be considered a leading candidate for the form to immobilize high-level wastes

Seismic-load-induced human errors and countermeasures using computer graphics in plant-operator communication

International Nuclear Information System (INIS)

Hara, Fumio

1988-01-01

This paper remarks the importance of seismic load-induced human errors in plant operation by delineating the characteristics of the task performance of human beings under seismic loads. It focuses on man-machine communication via multidimensional data like that conventionally displayed on large panels in a plant control room. It demonstrates a countermeasure to human errors using a computer graphics technique that conveys the global state of the plant operation to operators through cartoon-like, colored graphs in the form of faces that, with different facial expressions, show the plant safety status. (orig.)

Learning from the Learners: Preparing Future Teachers to Leverage the Benefits of Laptop Computers

Science.gov (United States)

Grundmeyer, Trent; Peters, Randal

2016-01-01

Technology is changing the teaching and learning landscape. Teacher preparation programs must produce teachers who have new skills and strategies to leverage the benefits of laptop computers in their classrooms. This study used a phenomenological strategy to explain first-year college students' perceptions of the effects of a 1:1 laptop experience…

Securing a cyber physical system in nuclear power plants using least square approximation and computational geometric approach

International Nuclear Information System (INIS)

Gawand, Hemangi Laxman; Bhattacharjee, A. K.; Roy, Kallol

2017-01-01

In industrial plants such as nuclear power plants, system operations are performed by embedded controllers orchestrated by Supervisory Control and Data Acquisition (SCADA) software. A targeted attack (also termed a control aware attack) on the controller/SCADA software can lead a control system to operate in an unsafe mode or sometimes to complete shutdown of the plant. Such malware attacks can result in tremendous cost to the organization for recovery, cleanup, and maintenance activity. SCADA systems in operational mode generate huge log files. These files are useful in analysis of the plant behavior and diagnostics during an ongoing attack. However, they are bulky and difficult for manual inspection. Data mining techniques such as least squares approximation and computational methods can be used in the analysis of logs and to take proactive actions when required. This paper explores methodologies and algorithms so as to develop an effective monitoring scheme against control aware cyber attacks. It also explains soft computation techniques such as the computational geometric method and least squares approximation that can be effective in monitor design. This paper provides insights into diagnostic monitoring of its effectiveness by attack simulations on a four-tank model and using computation techniques to diagnose it. Cyber security of instrumentation and control systems used in nuclear power plants is of paramount importance and hence could be a possible target of such applications

Securing a cyber physical system in nuclear power plants using least square approximation and computational geometric approach

Energy Technology Data Exchange (ETDEWEB)

Gawand, Hemangi Laxman [Homi Bhabha National Institute, Computer Section, BARC, Mumbai (India); Bhattacharjee, A. K. [Reactor Control Division, BARC, Mumbai (India); Roy, Kallol [BHAVINI, Kalpakkam (India)

2017-04-15

In industrial plants such as nuclear power plants, system operations are performed by embedded controllers orchestrated by Supervisory Control and Data Acquisition (SCADA) software. A targeted attack (also termed a control aware attack) on the controller/SCADA software can lead a control system to operate in an unsafe mode or sometimes to complete shutdown of the plant. Such malware attacks can result in tremendous cost to the organization for recovery, cleanup, and maintenance activity. SCADA systems in operational mode generate huge log files. These files are useful in analysis of the plant behavior and diagnostics during an ongoing attack. However, they are bulky and difficult for manual inspection. Data mining techniques such as least squares approximation and computational methods can be used in the analysis of logs and to take proactive actions when required. This paper explores methodologies and algorithms so as to develop an effective monitoring scheme against control aware cyber attacks. It also explains soft computation techniques such as the computational geometric method and least squares approximation that can be effective in monitor design. This paper provides insights into diagnostic monitoring of its effectiveness by attack simulations on a four-tank model and using computation techniques to diagnose it. Cyber security of instrumentation and control systems used in nuclear power plants is of paramount importance and hence could be a possible target of such applications.

Securing a Cyber Physical System in Nuclear Power Plants Using Least Square Approximation and Computational Geometric Approach

Directory of Open Access Journals (Sweden)

Hemangi Laxman Gawand

2017-04-01

Full Text Available In industrial plants such as nuclear power plants, system operations are performed by embedded controllers orchestrated by Supervisory Control and Data Acquisition (SCADA software. A targeted attack (also termed a control aware attack on the controller/SCADA software can lead a control system to operate in an unsafe mode or sometimes to complete shutdown of the plant. Such malware attacks can result in tremendous cost to the organization for recovery, cleanup, and maintenance activity. SCADA systems in operational mode generate huge log files. These files are useful in analysis of the plant behavior and diagnostics during an ongoing attack. However, they are bulky and difficult for manual inspection. Data mining techniques such as least squares approximation and computational methods can be used in the analysis of logs and to take proactive actions when required. This paper explores methodologies and algorithms so as to develop an effective monitoring scheme against control aware cyber attacks. It also explains soft computation techniques such as the computational geometric method and least squares approximation that can be effective in monitor design. This paper provides insights into diagnostic monitoring of its effectiveness by attack simulations on a four-tank model and using computation techniques to diagnose it. Cyber security of instrumentation and control systems used in nuclear power plants is of paramount importance and hence could be a possible target of such applications.

Evaluation of the fracture resistance of computer-aided design/computer-aided manufacturing monolithic crowns prepared in different cement thicknesses.

Science.gov (United States)

Sagsoz, N Polat; Yanıkoglu, N

2018-04-01

The purpose of this study was to evaluate the fracture resistance of monolithic computer-aided design/computer-aided manufacturing (CAD/CAM) crowns that are prepared with different cement thickness. For this investigation, a human maxillary premolar tooth was selected. Master model preparation was performed with a demand bur under water spray. Master die was taken to fabricate 105 epoxy resin replicas. The crowns were milled using a CEREC 4 CAD/CAM system (Software Version, 4.2.0.57192). CAD/CAM crowns were made using resin nanoceramic, feldspathic glass ceramic, lithium disilicate, and leucite-reinforced ceramics. Each group was subdivided into three groups in accordance with three different cement thicknesses (30, 90, and 150 μm). Crowns milled out. Then RelyX ™ U200 was used as a luting agent to bond the crowns to the prepared samples. After one hour cementations, the specimens were stored in water bath at 37°C for 1 week before testing. Seven unprepared and unrestored teeth were kept and tested as a control group. A universal test machine was used to assume the fracture resistance of all specimens. The compressive load (N) that caused fracture was recorded for each specimen. Fracture resistance data were statistically analyzed by one-way ANOVA and two-factor interaction modeling test (α = 0.001). There are statistically significant differences between fracture resistances of CAD/CAM monolithic crown materials (P cement thickness is not statistically significant for fracture resistance of CAD/CAM monolithic crowns (P > 0.001). CAD/CAM monolithic crown materials affected fracture resistance. Cement thickness (30, 90, and 150 μm) was not effective on fracture resistance of CAD/CAM monolithic crowns.

Computer based plant display and digital control system of Wolsong NPP Tritium Removal Facility

International Nuclear Information System (INIS)

Jung, C.; Smith, B.; Tosello, G.; Grosbois, J. de; Ahn, J.

2007-01-01

The Wolsong Tritium Removal Facility (WTRF) is an AECL-designed, first-of-a-kind facility that removes tritium from the heavy water that is used in systems of the CANDUM reactors in operation at the Wolsong Nuclear Power Plant in South Korea. The Plant Display and Control System (PDCS) provides digital plant monitoring and control for the WTRF and offers the advantages of state-of-the-art digital control system technologies for operations and maintenance. The overall features of the PDCS will be described and some of the specific approaches taken on the project to save construction time and costs, to reduce in-service life-cycle costs and to improve quality will be presented. The PDCS consists of two separate computer sub-systems: the Digital Control System (DCS) and the Plant Display System (PDS). The PDS provides the computer-based Human Machine Interface (HMI) for operators, and permits efficient supervisory or device level monitoring and control. A System Maintenance Console (SMC) is included in the PDS for the purpose of software and hardware configuration and on-line maintenance. A Historical Data System (HDS) is also included in the PDS as a data-server that continuously captures and logs process data and events for long-term storage and on-demand selective retrieval. The PDCS of WTRF has been designed and implemented based on an off-the-self PDS/DCS product combination, the Delta-V System from Emerson. The design includes fully redundant Ethernet network communications, controllers, power supplies and redundancy on selected I/O modules. The DCS provides field bus communications to interface with 3rd party controllers supplied on specialized skids, and supports HART communication with field transmitters. The DCS control logic was configured using a modular and graphical approach. The control strategies are primarily device control modules implemented as autonomous control loops, and implemented using IEC 61131-3 Function Block Diagram (FBD) and Structured

Development of computer-aided design and production system for nuclear power plant

International Nuclear Information System (INIS)

Ishii, Masanori

1983-01-01

The technically required matters related to the design and production of nuclear power stations tended to increase from the viewpoint of the safety and reliability, and it is indispensable to cope with such technically required matters skillfully for the rationalization of the design and production and for the construction of highly reliable plants. Ishikawajima Harima Heavy Industries Co., Ltd., has developed the computer-aided design data information and engineering system which performs dialogue type design and drawing, and as the result, the design-production consistent system is developed to do stress analysis, production design, production management and the output of data for numerically controlled machine tools consistently. In this paper, mainly the consistent system in the field of plant design centering around piping and also the computer system for the design of vessels and others are outlined. The features of the design works for nuclear power plants, the rationalization of the design and production management of piping and vessels, and the application of the CAD system to other general equipment and improvement works are reported. This system is the powerful means to meet the requirement of heightening quality and reducing cost. (Kako, I.)

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

Use of computational modeling in preparation and evaluation of surface imprinted xerogels for binding tetracycline

International Nuclear Information System (INIS)

Pace, Samantha J.; Nguyen, Eric; Baria, Maximillian P.; Mojica, Elmer-Rico E.

2015-01-01

Linear alkyl alkoxysilanes (methoxy and ethoxy-based) of varying length were used in preparing tetracycline surface imprinted silica xerogels by the sol–gel process. The resulting xerogels were characterized in terms of binding tetracycline (TC) by using tritium-labeled TC. Results showed preferential binding in the ethoxysilane based xerogels in comparison to methoxysilane based xerogels. A computational approach using the interaction energy (IE) between TC and each alkyl alkoxysilane was deduced as a rational way of predicting the formulation that would provide the best analytical performance for a given molecularly imprinted xerogel (MIX). Hartree-Fock calculations revealed an increase in IE as the length of the carbon chain increases until an optimum value at C6 in both alkoxysilanes. This is consistent with the experimental results wherein the C6 xerogel formulation has the highest imprinting factor. These results show the potential of using computational modeling as a rational way of preparing surface imprinted materials. (author)

IMPROVING TACONITE PROCESSING PLANT EFFICIENCY BY COMPUTER SIMULATION, Final Report

Energy Technology Data Exchange (ETDEWEB)

William M. Bond; Salih Ersayin

2007-03-30

This project involved industrial scale testing of a mineral processing simulator to improve the efficiency of a taconite processing plant, namely the Minorca mine. The Concentrator Modeling Center at the Coleraine Minerals Research Laboratory, University of Minnesota Duluth, enhanced the capabilities of available software, Usim Pac, by developing mathematical models needed for accurate simulation of taconite plants. This project provided funding for this technology to prove itself in the industrial environment. As the first step, data representing existing plant conditions were collected by sampling and sample analysis. Data were then balanced and provided a basis for assessing the efficiency of individual devices and the plant, and also for performing simulations aimed at improving plant efficiency. Performance evaluation served as a guide in developing alternative process strategies for more efficient production. A large number of computer simulations were then performed to quantify the benefits and effects of implementing these alternative schemes. Modification of makeup ball size was selected as the most feasible option for the target performance improvement. This was combined with replacement of existing hydrocyclones with more efficient ones. After plant implementation of these modifications, plant sampling surveys were carried out to validate findings of the simulation-based study. Plant data showed very good agreement with the simulated data, confirming results of simulation. After the implementation of modifications in the plant, several upstream bottlenecks became visible. Despite these bottlenecks limiting full capacity, concentrator energy improvement of 7% was obtained. Further improvements in energy efficiency are expected in the near future. The success of this project demonstrated the feasibility of a simulation-based approach. Currently, the Center provides simulation-based service to all the iron ore mining companies operating in northern

The analysis of the computer technologies used during preparation of sportsmen, specializing bodybuilding

OpenAIRE

Sedljar J.V.

2009-01-01

The generalized data about directions of information technologies use in sports practice are cited in the article. The opportunities of information-methodical system "Athlete" use in system of bodybuilder's preparation are examined in details. Program "Athlete" is a collection of tools, methods of automated data collection, processing, storage and use of information, with access to various information resources, including Internet. The prospects of computer technologies use in educational-tra...

The preparation and implementation of the commissioning of Qinshan nuclear power plant

International Nuclear Information System (INIS)

Huang Jinyuan

1993-05-01

The commissioning test of Qinshan Nuclear Power Plant is summarized. The preparation stage includes the organizations, commissioning programme, network planning, commissioning items, management procedures, responsibilities and interfaces between divisions, products ordering and supplying, personal training, quality assurance and the review and supervision by National Nuclear Safety Administration etc. The implementation stage includes the commissioning programme planning, intermediate hand-over inspection of the system and equipment, inspecting conditions and setting organizations for commissioning, the transition from commissioning to operating. Finally, some experiences in the commissioning test are presented in the article

A computer-assisted personalized approach in an undergraduate plant physiology class

Science.gov (United States)

Artus; Nadler

1999-04-01

We used Computer-Assisted Personalized Approach (CAPA), a networked teaching and learning tool that generates computer individualized homework problem sets, in our large-enrollment introductory plant physiology course. We saw significant improvement in student examination performance with regular homework assignments, with CAPA being an effective and efficient substitute for hand-graded homework. Using CAPA, each student received a printed set of similar but individualized problems of a conceptual (qualitative) and/or quantitative nature with quality graphics. Because each set of problems is unique, students were encouraged to work together to clarify concepts but were required to do their own work for credit. Students could enter answers multiple times without penalty, and they were able to obtain immediate feedback and hints until the due date. These features increased student time on task, allowing higher course standards and student achievement in a diverse student population. CAPA handles routine tasks such as grading, recording, summarizing, and posting grades. In anonymous surveys, students indicated an overwhelming preference for homework in CAPA format, citing several features such as immediate feedback, multiple tries, and on-line accessibility as reasons for their preference. We wrote and used more than 170 problems on 17 topics in introductory plant physiology, cataloging them in a computer library for general access. Representative problems are compared and discussed.

Development of a Computational Tool for Measuring Organizational Competitiveness in the Photovoltaic Power Plants

Directory of Open Access Journals (Sweden)

Carmen B. Rosa

2018-04-01

Full Text Available Photovoltaic (PV power generation is embedded in a globally competitive environment. This characteristic forces PV power plants to perform most processes relevant for their competitiveness with maximum efficiency. From managers’ point of view, the evaluation of solar energy performance from installed plants is justified to indicate their level of organizational competitiveness, which supports the decision-making process. This manuscript purposes a computational tool that graphically presents the level of competitiveness of PV power plants units based on performance indicators. This tool was developed by using the Key Performance Indicators (KPIs concept, which represents a set of measures focusing on the most critical aspects for the success of the organizations. The KPIs encompass four Fundamental Viewpoints (FV: Strategic Alliances, Solar Energy Monitoring, Management and Strategic Processes, and Power Generation Innovations. These four FVs were deployed on 26 Critical Success Factors (CSFs and 39 KPIs. Sequentially, the tool was applied in four solar generation plants, where three presented an organizational competitiveness global level “potentially competitive”. The proposed computational tool allows managers to assess the degree of organization competitiveness as well as aid in prospecting of future scenarios and decision-making.

Nuclear plant analyzer: An efficient tool for training and operational analyses

International Nuclear Information System (INIS)

Bartsoen, L.; Mandy, C.; Stubbe, E.

1999-01-01

The advanced computer technology available now at low cost, combined with the maturity of the best-estimate engineering codes are the fundamentals of the Nuclear Plant Analyzer (NPA). At Tractebel Energy Engineering (TEE), the RELAP5 advanced thermal-hydraulics code is used as basis for the NPA that is mainly used for the training of simulator instructors and plant personnel. Using the special graphical features of the NPA, a set of six course modules has been prepared to provide an in-depth physical understanding of the main thermal-hydraulic phenomena that dominate nuclear power plant behavior in normal and accidental plant conditions. (author)

Design concepts and experience in the application of distributed computing to the control of large CEGB power plant

International Nuclear Information System (INIS)

Wallace, J.N.

1980-01-01

With the ever increasing price of fossil fuels it became obvious during the 1970's that Pembroke Power Station (4 x 500MW oil fired) and Didcot Power Station (4 x 500MW coal fired) were going to operate flexibly with many units two-shifting frequently. The region was also expecting to refurbish nuclear plant in the 1980's. Based on previous experience with mini-computers, the region initiated a research/development programme aimed at refitting Pembroke and Didcot using distrubuted computer techniques that were also broadly applicable to nuclear plant. Major schemes have now been implemented at Pembroke and Didcot for plant condition monitoring, control and display. All computers on two units at each station are now functional with a third unit currently being set to work. This paper aims to outline the generic technical aspects of these schemes, describe the implementation strategy adopted and develop some thoughts on nuclear power plant applications. (auth)

Preparation of emergency care centre exercises

International Nuclear Information System (INIS)

Schnadt, H.; Miska, H.

2011-01-01

Setup and operation of emergency care centres (sometimes also addressed as emergency reception centres) are part of emergency response in the environs of nuclear power plants. The preparation of an exercise scenario for such a centre is very demanding on the responsible agency. Therefore, a computer code has been developed which helps to translate the exercise objectives into instructions for figurants which simulate the affected population. These instructions are intended to steer a determined flow of people through the emergency care centre by providing fictitious radiological readings and by injecting the demand for additional actions of response personnel by statements and questions. (orig.)

A Comparative Study of Sample Preparation for Staining and Immunodetection of Plant Cell Walls by Light Microscopy

Science.gov (United States)

Verhertbruggen, Yves; Walker, Jesse L.; Guillon, Fabienne; Scheller, Henrik V.

2017-01-01

Staining and immunodetection by light microscopy are methods widely used to investigate plant cell walls. The two techniques have been crucial to study the cell wall architecture in planta, its deconstruction by chemicals or cell wall-degrading enzymes. They have been instrumental in detecting the presence of cell types, in deciphering plant cell wall evolution and in characterizing plant mutants and transformants. The success of immunolabeling relies on how plant materials are embedded and sectioned. Agarose coating, wax and resin embedding are, respectively, associated with vibratome, microtome and ultramicrotome sectioning. Here, we have systematically carried out a comparative analysis of these three methods of sample preparation when they are applied for cell wall staining and cell wall immunomicroscopy. In order to help the plant community in understanding and selecting adequate methods of embedding and sectioning for cell wall immunodetection, we review in this article the advantages and limitations of these three methods. Moreover, we offer detailed protocols of embedding for studying plant materials through microscopy. PMID:28900439

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

Expanding Capacity and Promoting Inclusion in Introductory Computer Science: A Focus on Near-Peer Mentor Preparation and Code Review

Science.gov (United States)

Pon-Barry, Heather; Packard, Becky Wai-Ling; St. John, Audrey

2017-01-01

A dilemma within computer science departments is developing sustainable ways to expand capacity within introductory computer science courses while remaining committed to inclusive practices. Training near-peer mentors for peer code review is one solution. This paper describes the preparation of near-peer mentors for their role, with a focus on…

Plant process computer system upgrades at the KSG simulator centre

International Nuclear Information System (INIS)

2006-01-01

The human-machine interface (HMI) of a modern plant process computer system (PPC) differs significantly from that of older systems. Along with HMI changes, there are often improvements to system functionality such as alarm display and printing functions and transient data analysis capabilities. Therefore, the upgrade or replacement of a PPC in the reference plant will typically require an upgrade of the simulator (see Section 6.5.1 for additional information). Several options are available for this type of project including stimulation of a replica system,or emulation, or simulation of PPC functionality within the simulation environment. To simulate or emulate a PCC, detailed knowledge of hardware and software functionality is required. This is typically vendor proprietary information, which leads to licensing and other complications. One of the added benefits of stimulating the PPC system is that the simulator can be used as a test bed for functional testing (i.e. verification and validation) of the system prior to installation in the reference plant. Some of this testing may include validation of the process curve and system diagram displays. Over the past few years several German NPPs decided to modernize their plant process computer (PPC) systems. After the NPPs had selected the desired system to meet their requirements the question arose how to modernize the PPC systems on the corresponding simulators. Six German NPPs selected the same PPC system from the same vendor and it was desired to perform integral tests of the HMI on the simulators. In this case the vendor offered a stimulated variant of their system and it therefore made sense to choose that implementation method for upgrade of the corresponding simulators. The first simulator PPC modernization project can be considered as a prototype project for the follow-on projects. In general, from the simulator project execution perspective the implementation of several stimulated PPC systems of the same type

Computerization of operation and maintenance for nuclear power plants. Working material

International Nuclear Information System (INIS)

1994-01-01

This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. The technical document is the result of a series of advisory and consultant meetings held by the IAEA in Vienna in 1991 - 1994. The document was prepared with the participation of experts from Canada, France, Germany, Hungary, Japan, Russia, Sweden, United Kingdom, and the United States. Refs, figs and tabs

Computer program of iodine removal in the LWR containment vessel under LOCA conditions, MIRA-PB

International Nuclear Information System (INIS)

Nishio, Gunji; Tanaka, Mitsugu; Tamura, Tomohiko.

1978-03-01

LWR plants have a containment system for reactor safety consisting of spray and air cleaning filter. R.L.Ritzman of Battele Columbus Lab. developed computer code MIRAP/MIRAB for predicting iodine removal by containment system for PWR and BWR; which has some problem, however. The computer code MIRA-PB prepared by the authors is a modification of MIRAP/MIRAB. (auth.)

Preparing Future Secondary Computer Science Educators

Science.gov (United States)

Ajwa, Iyad

2007-01-01

Although nearly every college offers a major in computer science, many computer science teachers at the secondary level have received little formal training. This paper presents details of a project that could make a significant contribution to national efforts to improve computer science education by combining teacher education and professional…

Preparation of Grinding Aid Using Waste Acid Residue from Plasticizer Plant

Science.gov (United States)

Li, Lingxiao; Feng, Yanchao; Liu, Manchao; Zhao, Fengqing

2017-09-01

The grinding aid for granulated blast-furnace slag were prepared from waste acid residue from plasticizer plant through neutralization, de-methanol and granulation process. In this process, sulfuric acid was transformed into gypsum which has much contribution for grinding effect by combined use with the glycerol and poly glycerin in the waste. Fly ash was used for granulation for the composite grinding aid. Methanol can be recycled in the process. The result showed that the suitable addition of grinding aid is 0.03 % of granulated blast-furnace slag (mass). In this case, the specific surface area is 14% higher than that of the blank. Compared with the common grinding aids, it has excellent performance and low cost.

Computer systems for thermal power plant operation and management; Karyoku hatsudensho no kodo joho system

Energy Technology Data Exchange (ETDEWEB)

Adachi, M.; Miyabe, K.; Matsumoto, A. [Toshiba Corp., Tokyo (Japan)

1997-07-01

To improve on work efficiency by pooling information and prompting the transmission of information at thermal power stations, efforts have been under way for some years to realize a working environment in which everyone is provided with a computer exclusively for one`s own use. Toshiba Corporation believes that the coming information system has to be equipped with two features of on-demand and EUC (end user computing). Introduced in this report are some approaches to systems that will take care of plant operation information and facility information making use of Toshiba`s advanced information system GS7000XP series. Plant operation information is categorized into process data, operation history data, checking patrol data, and periodic inspection data and, for instance, a distributed-type management computer provided with data recording and application processing servers is used for handling operation history data. For the collection of facility information, efforts are being made to establish a computer network step by step for exchanging information with manufacturers and associated businesses. 3 refs., 4 figs., 1 tab.

Evaluation of specimen preparation techniques for micro-PIXE localisation of elements in hyperaccumulating plants

International Nuclear Information System (INIS)

Kachenko, Anthony G.; Siegele, Rainer; Bhatia, Naveen P.; Singh, Balwant; Ionescu, Mihail

2008-01-01

Hybanthus floribundus subsp. floribundus, a rare Australian Ni-hyperaccumulating shrub and Pityrogramma calomelanos var. austroamericana, an Australian naturalized As-hyperaccumulating fern are promising species for use in phytoremediation of contaminated sites. Micro-proton-induced X-ray emission (μ-PIXE) spectroscopy was used to map the elemental distribution of the accumulated metal(loid)s, Ca and K in leaf or pinnule tissues of the two plant species. Samples were prepared by two contrasting specimen preparation techniques: freeze-substitution in tetrahydrofuran (THF) and freeze-drying. The specimens were analysed to compare the suitability of each technique in preserving (i) the spatial elemental distribution and (ii) the tissue structure of the specimens. Further, the μ-PIXE results were compared with concentration of elements in the bulk tissue obtained by ICP-AES analysis. In H. floribundus subsp. floribundus, μ-PIXE analysis revealed Ni, Ca and K concentrations in freeze-dried leaf tissues were at par with bulk tissue concentrations. Elemental distribution maps illustrated that Ni was preferentially localised in the adaxial epidermal tissues (1% DW) and least concentration was found in spongy mesophyll tissues (0.53% DW). Conversely, elemental distribution maps of THF freeze-substituted tissues indicated significantly lower Ni, Ca and K concentrations than freeze-dried specimens and bulk tissue concentrations. Moreover, Ni concentrations were uniform across the whole specimen and no localisation was observed. In P. calomelanos var. austroamericana freeze-dried pinnule tissues, μ-PIXE revealed statistically similar As, Ca and K concentrations as compared to bulk tissue concentrations. Elemental distribution maps showed that As localisation was relatively uniform across the whole specimen. Once again, THF freeze-substituted tissues revealed a significant loss of As compared to freeze-dried specimens and the concentrations obtained by bulk tissue analysis

Development of distributed computer systems for future nuclear power plants

International Nuclear Information System (INIS)

Yan, G.; L'Archeveque, J.V.R.

1978-01-01

Dual computers have been used for direct digital control in CANDU power reactors since 1963. However, as reactor plants have grown in size and complexity, some drawbacks to centralized control appear such as, for example, the surprisingly large amount of cabling required for information transmission. Dramatic changes in costs of components and a desire to improve system performance have stimulated a broad-based research and development effort in distribution systems. This paper outlines work in this area

A COMPUTATIONAL WORKBENCH ENVIRONMENT FOR VIRTUAL POWER PLANT SIMULATION

Energy Technology Data Exchange (ETDEWEB)

Mike Bockelie; Dave Swensen; Martin Denison; Adel Sarofim; Connie Senior

2004-12-22

, immersive environment. The Virtual Engineering Framework (VEF), in effect a prototype framework, was developed through close collaboration with NETL supported research teams from Iowa State University Virtual Reality Applications Center (ISU-VRAC) and Carnegie Mellon University (CMU). The VEF is open source, compatible across systems ranging from inexpensive desktop PCs to large-scale, immersive facilities and provides support for heterogeneous distributed computing of plant simulations. The ability to compute plant economics through an interface that coupled the CMU IECM tool to the VEF was demonstrated, and the ability to couple the VEF to Aspen Plus, a commercial flowsheet modeling tool, was demonstrated. Models were interfaced to the framework using VES-Open. Tests were performed for interfacing CAPE-Open-compliant models to the framework. Where available, the developed models and plant simulations have been benchmarked against data from the open literature. The VEF has been installed at NETL. The VEF provides simulation capabilities not available in commercial simulation tools. It provides DOE engineers, scientists, and decision makers with a flexible and extensible simulation system that can be used to reduce the time, technical risk, and cost to develop the next generation of advanced, coal-fired power systems that will have low emissions and high efficiency. Furthermore, the VEF provides a common simulation system that NETL can use to help manage Advanced Power Systems Research projects, including both combustion- and gasification-based technologies.

Dynamics and control of nuclear power plants

International Nuclear Information System (INIS)

Tomsic, M.; Mavko, B.; Aleksic, U.; Stritar, A.; Adrinek, R.

1977-01-01

A mathematical model of the power plant with a pressurized water reactor has been prepared and tested. The model is intended for a schematic simulator based on a digital computer. The results of the simulation run for various normal transients are in good agreement with literature data. Equipment for computer control of the experimental reactor TRIGA has been completed. The equipment includes two microcomputers and associated interface circuits. Presently, only data logging is performed. The analyses of random signals on the TRIGA reactor have been continued. Measurements of neutron flux, fuel temperature and cooling water duct have been performed

Accumulation and preparation of nondestructive inspection data for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

In recent years, flaws due to stress corrosion cracking (SCC) in stainless steel piping and nickel based alloy welds were detected at nuclear power plants in Japan. Weld Overlay (WOL) has been developed as a repairing method for piping items without removing flaws. Since the inspection techniques for WOL pipes and nickel based alloy welds are not verified enough in Japan, Japan Nuclear Energy Safety Organization (JNES) has been carrying out a six year research project entitled 'Accumulation and Preparation of Nondestructive Inspection Data for Nuclear Power Plants' regarding nondestructive inspection since FY2007. In this research project, detection and sizing capability of SCC by Ultrasonic Testing (UT) are evaluated using mockup tests. In addition, the results of this project and past nondestructive inspection data performed by JNES projects are gathered, and inputted into the database of NDT information. In FY2012, followings were conducted. 1) Analysis for UT measurement results of nickel based alloy weld simulating safe end of reactor vessel outlet nozzle. 2) Analysis for UT measurement results of cast stainless steel piping. 3) Development of interface of UT simulation. 4) Development of nondestructive testing guideline. (author)

Computer-based liquid radioactive waste control with plant emergency and generator temperature monitoring

International Nuclear Information System (INIS)

Plotnick, R.J.; Schneider, M.I.; Shaffer, C.E.

1986-01-01

At the start of the design of the liquid radwaste control system for a nuclear generating station under construction, several serious problems were detected. The solution incorporated a new approach utilizing a computer and a blend of standard and custom software to replace the existing conventionally instrumented benchboard. The computer-based system, in addition to solving the problems associated with the benchboard design, also provided other enhancements which significantly improved the operability and reliability of the radwaste system. The functionality of the computer-based radwaste control system also enabled additional applications to be added to an expanded multitask version of the radwaste computer: 1) a Nuclear Regulatory Commission (NRC) requirement that all nuclear power plants have an emergency response facility status monitoring system; and 2) the sophisticated temperature monitoring and trending requested by the electric generator manufacturer to continue its warranty commitments. The addition of these tasks to the radwaste computer saved the cost of one or more computers that would be dedicated to these work requirements

The numerical computation of seismic fragility of base-isolated Nuclear Power Plants buildings

International Nuclear Information System (INIS)

Perotti, Federico; Domaneschi, Marco; De Grandis, Silvia

2013-01-01

Highlights: • Seismic fragility of structural components in base isolated NPP is computed. • Dynamic integration, Response Surface, FORM and Monte Carlo Simulation are adopted. • Refined approach for modeling the non-linearities behavior of isolators is proposed. • Beyond-design conditions are addressed. • The preliminary design of the isolated IRIS is the application of the procedure. -- Abstract: The research work here described is devoted to the development of a numerical procedure for the computation of seismic fragilities for equipment and structural components in Nuclear Power Plants; in particular, reference is made, in the present paper, to the case of isolated buildings. The proposed procedure for fragility computation makes use of the Response Surface Methodology to model the influence of the random variables on the dynamic response. To account for stochastic loading, the latter is computed by means of a simulation procedure. Given the Response Surface, the Monte Carlo method is used to compute the failure probability. The procedure is here applied to the preliminary design of the Nuclear Power Plant reactor building within the International Reactor Innovative and Secure international project; the building is equipped with a base isolation system based on the introduction of High Damping Rubber Bearing elements showing a markedly non linear mechanical behavior. The fragility analysis is performed assuming that the isolation devices become the critical elements in terms of seismic risk and that, once base-isolation is introduced, the dynamic behavior of the building can be captured by low-dimensional numerical models

The analysis of the computer technologies used during preparation of sportsmen, specializing bodybuilding

Directory of Open Access Journals (Sweden)

Sedljar J.V.

2009-10-01

Full Text Available The generalized data about directions of information technologies use in sports practice are cited in the article. The opportunities of information-methodical system "Athlete" use in system of bodybuilder's preparation are examined in details. Program "Athlete" is a collection of tools, methods of automated data collection, processing, storage and use of information, with access to various information resources, including Internet. The prospects of computer technologies use in educational-training process of the sportsmen specializing in bodybuilding are designated.

Use of digital computers in the protection system for Savannah River reactors

International Nuclear Information System (INIS)

Gimmy, K.L.

1977-06-01

Each production reactor at the Savannah River Plant has recently been provided with a protective system using dual digital computers. The dual ''safety computers'' monitor coolant temperature and flow in each of the 600 fuel assemblies in the reactor. The system provides alarms and automatic reactor shutdown (SCRAM) if these variables exceed predetermined setpoints. The system provides the primary protection for unwanted local or general power increase or assembly coolant flow reduction. Standard process control computers are used and all scanning, data output, and protective action are controlled by software prepared by Du Pont

Preparation of antioxidant enzymatic hydrolysates from honeybee-collected pollen using plant enzymes.

Science.gov (United States)

Marinova, Margarita D; Tchorbanov, Bozhidar P

2011-01-09

Enzymatic hydrolysates of honeybee-collected pollen were prepared using food-grade proteinase and aminopeptidases entirely of plant origin. Bromelain from pineapple stem was applied (8 mAU/g substrate) in the first hydrolysis stage. Aminopeptidase (0.05 U/g substrate) and proline iminopeptidase (0.03 U/g substrate) from cabbage leaves (Brassica oleracea var. capitata), and aminopeptidase (0.2 U/g substrate) from chick-pea cotyledons (Cicer arietinum L.) were involved in the additional hydrolysis of the peptide mixtures. The degree of hydrolysis (DH), total phenolic contents, and protein contents of these hydrolysates were as follows: DH (about 20-28%), total phenolics (15.3-27.2 μg/mg sample powder), and proteins (162.7-242.8 μg/mg sample powder), respectively. The hydrolysates possessed high antiradical scavenging activity determined with DPPH (42-46% inhibition). The prepared hydrolysates of bee-collected flower pollen may be regarded as effective natural and functional dietary food supplements due to their remarkable content of polyphenol substances and significant radical-scavenging capacity with special regard to their nutritional-physiological implications.

PLEXFIN a computer model for the economic assessment of nuclear power plant life extension. User's manual

International Nuclear Information System (INIS)

2007-01-01

The IAEA developed PLEXFIN, a computer model analysis tool aimed to assist decision makers in the assessment of the economic viability of a nuclear power plant life/licence extension. This user's manual was produced to facilitate the application of the PLEXFIN computer model. It is widely accepted in the industry that the operational life of a nuclear power plant is not limited to a pre-determined number of years, sometimes established on non-technical grounds, but by the capability of the plant to comply with the nuclear safety and technical requirements in a cost effective manner. The decision to extend the license/life of a nuclear power plant involves a number of political, technical and economic issues. The economic viability is a cornerstone of the decision-making process. In a liberalized electricity market, the economics to justify a nuclear power plant life/license extension decision requires a more complex evaluation. This user's manual was elaborated in the framework of the IAEA's programmes on Continuous process improvement of NPP operating performance, and on Models for analysis and capacity building for sustainable energy development, with the support of four consultants meetings

A Computer-Assisted Personalized Approach in an Undergraduate Plant Physiology Class1

Science.gov (United States)

Artus, Nancy N.; Nadler, Kenneth D.

1999-01-01

We used Computer-Assisted Personalized Approach (CAPA), a networked teaching and learning tool that generates computer individualized homework problem sets, in our large-enrollment introductory plant physiology course. We saw significant improvement in student examination performance with regular homework assignments, with CAPA being an effective and efficient substitute for hand-graded homework. Using CAPA, each student received a printed set of similar but individualized problems of a conceptual (qualitative) and/or quantitative nature with quality graphics. Because each set of problems is unique, students were encouraged to work together to clarify concepts but were required to do their own work for credit. Students could enter answers multiple times without penalty, and they were able to obtain immediate feedback and hints until the due date. These features increased student time on task, allowing higher course standards and student achievement in a diverse student population. CAPA handles routine tasks such as grading, recording, summarizing, and posting grades. In anonymous surveys, students indicated an overwhelming preference for homework in CAPA format, citing several features such as immediate feedback, multiple tries, and on-line accessibility as reasons for their preference. We wrote and used more than 170 problems on 17 topics in introductory plant physiology, cataloging them in a computer library for general access. Representative problems are compared and discussed. PMID:10198076

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

Computer modeling of ground-water flow at the Savannah River Plant

International Nuclear Information System (INIS)

Root, R.W. Jr.

1979-01-01

Mathematical equations describing ground-water flow are used in a computer model being developed to predict the space-time distribution of hydraulic head beneath a part of the Savannah River Plant site. These equations are solved by a three-dimensional finite-difference scheme. Preliminary calibration of the hydraulic head model has been completed and calculated results compare well with water-level changes observed in the field. 10 figures, 1 table

Preparation and properties of SYNROC D containing simulated Savannah River Plant high-level defense waste

International Nuclear Information System (INIS)

Hoenig, C.; Rozsa, R.; Bazan, F.; Otto, R.; Grens, J.

1981-01-01

We describe in detail the formulation and processing steps used to prepare all SYNROC D samples tested in the Comparative Leach Testing Program at the Savannah River Laboratory. We also discuss how the composition of the Savannah River Plant sludge influences the formulation and ultimate preparation of SYNROC D. Mechanical properties are reported in the categories of elastic constants, flexural and compressive strengths, and microhardness; thermal expansion and thermal conductivity results are presented. The thermal expansion data indicated the presence of significant residual strain and the possibility of an unidentified amorphous or glassy phase in the microstructure. We summarize the standardized (MCC) leaching results for both crushed Synroc and monoliths in deionized water, silicate water, and salt brine at 90 0 C and 150 0 C

Computer-aided stress analysis system for nuclear plant primary components

International Nuclear Information System (INIS)

Murai, Tsutomu; Tokumaru, Yoshio; Yamazaki, Junko.

1980-06-01

Generally it needs a vast quantity of calculation to make the stress analysis reports of nuclear plant primary components. In Japan, especially, stress analysis reports are under obligation to make for each plant. In Mitsubishi Heavy Industries, Ltd., We have been making great efforts to rationalize the process of analysis for about these ten years. As the result of rationalization up to now, a computer-aided stress analysis system using graphic display, graphic tablet, data file, etc. was accomplished and it needs us only the least hand work. In addition we developed a fracture safety analysis system. And we are going to develop the input generator system for 3-dimensional FEM analysis by graphics terminals in the near future. We expect that when the above-mentioned input generator system is accomplished, it will be possible for us to solve instantly any case of problem. (author)

75 FR 29575 - Endangered and Threatened Wildlife and Plants; Indiana Bat; Notice of Intent To Prepare a Draft...

Science.gov (United States)

2010-05-26

... hibernation, and possibly pesticides. An additional and emerging threat to Indiana bats is White-Nose Syndrome...] Endangered and Threatened Wildlife and Plants; Indiana Bat; Notice of Intent To Prepare a Draft Environmental... Indiana bat (Myotis sodalis), a Federal endangered species, from activities associated with the...

Viral Diagnostics in Plants Using Next Generation Sequencing: Computational Analysis in Practice

Directory of Open Access Journals (Sweden)

Susan Jones

2017-10-01

Full Text Available Viruses cause significant yield and quality losses in a wide variety of cultivated crops. Hence, the detection and identification of viruses is a crucial facet of successful crop production and of great significance in terms of world food security. Whilst the adoption of molecular techniques such as RT-PCR has increased the speed and accuracy of viral diagnostics, such techniques only allow the detection of known viruses, i.e., each test is specific to one or a small number of related viruses. Therefore, unknown viruses can be missed and testing can be slow and expensive if molecular tests are unavailable. Methods for simultaneous detection of multiple viruses have been developed, and (NGS is now a principal focus of this area, as it enables unbiased and hypothesis-free testing of plant samples. The development of NGS protocols capable of detecting multiple known and emergent viruses present in infected material is proving to be a major advance for crops, nuclear stocks or imported plants and germplasm, in which disease symptoms are absent, unspecific or only triggered by multiple viruses. Researchers want to answer the question “how many different viruses are present in this crop plant?” without knowing what they are looking for: RNA-sequencing (RNA-seq of plant material allows this question to be addressed. As well as needing efficient nucleic acid extraction and enrichment protocols, virus detection using RNA-seq requires fast and robust bioinformatics methods to enable host sequence removal and virus classification. In this review recent studies that use RNA-seq for virus detection in a variety of crop plants are discussed with specific emphasis on the computational methods implemented. The main features of a number of specific bioinformatics workflows developed for virus detection from NGS data are also outlined and possible reasons why these have not yet been widely adopted are discussed. The review concludes by discussing the future

Viral Diagnostics in Plants Using Next Generation Sequencing: Computational Analysis in Practice.

Science.gov (United States)

Jones, Susan; Baizan-Edge, Amanda; MacFarlane, Stuart; Torrance, Lesley

2017-01-01

Viruses cause significant yield and quality losses in a wide variety of cultivated crops. Hence, the detection and identification of viruses is a crucial facet of successful crop production and of great significance in terms of world food security. Whilst the adoption of molecular techniques such as RT-PCR has increased the speed and accuracy of viral diagnostics, such techniques only allow the detection of known viruses, i.e., each test is specific to one or a small number of related viruses. Therefore, unknown viruses can be missed and testing can be slow and expensive if molecular tests are unavailable. Methods for simultaneous detection of multiple viruses have been developed, and (NGS) is now a principal focus of this area, as it enables unbiased and hypothesis-free testing of plant samples. The development of NGS protocols capable of detecting multiple known and emergent viruses present in infected material is proving to be a major advance for crops, nuclear stocks or imported plants and germplasm, in which disease symptoms are absent, unspecific or only triggered by multiple viruses. Researchers want to answer the question "how many different viruses are present in this crop plant?" without knowing what they are looking for: RNA-sequencing (RNA-seq) of plant material allows this question to be addressed. As well as needing efficient nucleic acid extraction and enrichment protocols, virus detection using RNA-seq requires fast and robust bioinformatics methods to enable host sequence removal and virus classification. In this review recent studies that use RNA-seq for virus detection in a variety of crop plants are discussed with specific emphasis on the computational methods implemented. The main features of a number of specific bioinformatics workflows developed for virus detection from NGS data are also outlined and possible reasons why these have not yet been widely adopted are discussed. The review concludes by discussing the future directions of this

Careful determination of inservice inspection of piping by computer analysis in nuclear power plant

International Nuclear Information System (INIS)

Lim, H. T.; Lee, S. L.; Lee, J. P.; Kim, B. C.

1992-01-01

Stress analysis has been performed using computer program ANSYS in the pressurizer surge line in order to predict possibility of crack generation due to thermal stratification phenomena in pipes connected to reactor coolant system of Nuclear power plants. Highly vulnerable area to crack generation has been chosen by the analysis of fatigue due to thermal stress in pressurizer surge line. This kind of result can be helpful to choose the location requiring intensive care during inservice inspection of nuclear power plants.

Assessment of computer codes for VVER-440/213-type nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Szabados, L.; Ezsol, Gy.; Perneczky [Atomic Energy Research Institute, Budapest (Hungary)

1995-09-01

Nuclear power plant of VVER-440/213 designed by the former USSR have a number of special features. As a consequence of these features the transient behaviour of such a reactor system should be different from the PWR system behaviour. To study the transient behaviour of the Hungarian Paks Nuclear Power Plant of VVER-440/213-type both analytical and experimental activities have been performed. The experimental basis of the research in the PMK-2 integral-type test facility , which is a scaled down model of the plant. Experiments performed on this facility have been used to assess thermal-hydraulic system codes. Four tests were selected for {open_quotes}Standard Problem Exercises{close_quotes} of the International Atomic Energy Agency. Results of the 4th Exercise, of high international interest, are presented in the paper, focusing on the essential findings of the assessment of computer codes.

Manual of phosphoric acid fuel cell power plant cost model and computer program

Science.gov (United States)

Lu, C. Y.; Alkasab, K. A.

1984-01-01

Cost analysis of phosphoric acid fuel cell power plant includes two parts: a method for estimation of system capital costs, and an economic analysis which determines the levelized annual cost of operating the system used in the capital cost estimation. A FORTRAN computer has been developed for this cost analysis.

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

[Estimation of maximum acceptable concentration of lead and cadmium in plants and their medicinal preparations].

Science.gov (United States)

Zitkevicius, Virgilijus; Savickiene, Nijole; Abdrachmanovas, Olegas; Ryselis, Stanislovas; Masteiková, Rūta; Chalupova, Zuzana; Dagilyte, Audrone; Baranauskas, Algirdas

2003-01-01

Heavy metals (lead, cadmium) are possible dashes which quantity is defined by the limiting acceptable contents. Different drugs preparations: infusions, decoctions, tinctures, extracts, etc. are produced using medicinal plants. The objective of this research was to study the impurities of heavy metals (lead, cadmium) in medicinal plants and some drug preparations. We investigated liquid extracts of fruits Crataegus monogyna Jacq. and herbs of Echinacea purpurea Moench., tinctures--of herbs Leonurus cardiaca L. The raw materials were imported from Poland. Investigations were carried out in cooperation with the Laboratory of Antropogenic Factors of the Institute for Biomedical Research. Amounts of lead and cadmium were established after "dry" mineralisation using "Perkin-Elmer Zeeman/3030" model electrothermic atomic absorption spectrophotometer (ETG AAS/Zeeman). It was established that lead is absorbed most efficiently after estimation of absorption capacity of cellular fibers. About 10.73% of lead crosses tinctures and extracts, better cadmium--49.63%. Herbs of Leonurus cardiaca L. are the best in holding back lead and cadmium. About 14.5% of lead and cadmium crosses the tincture of herbs Leonurus cardiaca L. We estimated the factors of heavy metals (lead, cadmium) in the liquid extracts of Crataegus monogyna Jacq. and Echinacea purpurea Moench., tincture of Leonurus cardiaca L. after investigations of heavy metals (lead, cadmium) in drugs and preparations of it. The amounts of heavy metals (lead, cadmium) don't exceed the allowable norms in fruits of Crataegus monogyna Jacq., herbs of Leonurus cardiaca L. and Echinacea purpurea Moench. after estimation of lead and cadmium extraction factors, the maximum of acceptable daily intake and the quantity of drugs consumption in day.

Computer integrated construction at AB building in reprocessing plant

International Nuclear Information System (INIS)

Takami, Masahiro; Azuchi, Takehiro; Sekiguchi, Kenji

1999-01-01

JNFL (Japan Nuclear Fuel Limited) is now processing with construction of the spent nuclear fuel reprocessing plant at Rokkasho Village in Aomori Prefecture, which is coming near to the busiest period of construction. Now we are trying to complete the civil work of AB Building and KA Building in a very short construction term by applying CIC (Computer Integrated Construction) concept, in spite of its hard construction conditions, such as the massive and complicated building structure, interferences with M and E (Mechanical and Electrical) work, severe winter weather, remote site location, etc. The key technologies of CIC are three-dimensional CAD, information network, and prefabrication and mechanization of site work. (author)

3. General principles of assessing seismic resistance of technological equipment of nuclear power plants

International Nuclear Information System (INIS)

1983-01-01

The evaluation of the seismic resistance of technological equipment is performed by computation, experimental trial, possibly by combining both methods. Existing and prepared standards in the field of seismic resistance of nuclear power plants are mentioned. Accelerograms and response spectra of design-basis earhtquake and maximum credible earthquake serve as the basic data for evaluating seismic resistance. The nuclear power plant in Mochovce will be the first Czechoslovak nuclear power plant with so-called partially seismic design. The problem of dynamic interaction of technological equipment and nuclear power plant systems with a bearing structure is discussed. (E.F.)

Preparing and Conducting Review Missions of Instrumentation and Control Systems in Nuclear Power Plants

International Nuclear Information System (INIS)

2016-07-01

The IERICS (Independent Engineering Review of Instrumentation and Control Systems) mission is a comprehensive engineering review service directly addressing strategy and the key elements for implementation of modern instrumentation and control (I&C) systems, noting in applicable cases, specific concerns related to the implementation of advanced digital I&C systems and the use of software and/or digital logic in safety applications of a nuclear power plant. The guidelines outlined in this publication provide a basic structure, common reference and checklist across the various areas covered by an IERICS mission. Publications referenced in these guidelines could provide additional useful information for the counterpart while preparing for the IERICS mission. A structure for the mission report is given in the Appendix. In 2016, this publication was revised by international experts who had participated in previous IERICS missions. The revision reflects experiences and lessons learned from the preparation and conduct of those missions

Dispatcher's monitoring systems of coal preparation processes. Systemy dyspozytorskiej kontroli procesow wzbogacania wegla

Energy Technology Data Exchange (ETDEWEB)

Cierpisz, S [Politechnika Slaska, Gliwice (Poland); Cierpisz, T; Glowacki, D; Puczylowski, T [Min-Tech Sp. z o.o., Katowice (Poland)

1994-08-01

The computer-based control and dispatcher's monitoring systems for coal preparation plants are described. The article refers to the local automation systems of coal blending production, control systems of heavy media separation process and dispatcher's visualization systems of technological lines operation. The effects of implementation of the above mentioned systems as well as some experiences gained at the designing and operational stages are given. (author). 2 refs., 6 figs.

Preparation and properties of SYNROC D containing simulated Savannah River Plant high-level defense waste

Energy Technology Data Exchange (ETDEWEB)

Hoenig, C.; Rozsa, R.; Bazan, F.; Otto, R.; Grens, J.

1981-07-23

We describe in detail the formulation and processing steps used to prepare all SYNROC D samples tested in the Comparative Leach Testing Program at the Savannah River Laboratory. We also discuss how the composition of the Savannah River Plant sludge influences the formulation and ultimate preparation of SYNROC D. Mechanical properties are reported in the categories of elastic constants, flexural and compressive strengths, and microhardness; thermal expansion and thermal conductivity results are presented. The thermal expansion data indicated the presence of significant residual strain and the possibility of an unidentified amorphous or glassy phase in the microstructure. We summarize the standardized (MCC) leaching results for both crushed Synroc and monoliths in deionized water, silicate water, and salt brine at 90/sup 0/C and 150/sup 0/C.

Preparation of Antioxidant Enzymatic Hydrolysates from Honeybee-Collected Pollen Using Plant Enzymes

Directory of Open Access Journals (Sweden)

Margarita D. Marinova

2010-01-01

Full Text Available Enzymatic hydrolysates of honeybee-collected pollen were prepared using food-grade proteinase and aminopeptidases entirely of plant origin. Bromelain from pineapple stem was applied (8 mAU/g substrate in the first hydrolysis stage. Aminopeptidase (0.05 U/g substrate and proline iminopeptidase (0.03 U/g substrate from cabbage leaves (Brassica oleracea var. capitata, and aminopeptidase (0.2 U/g substrate from chick-pea cotyledons (Cicer arietinum L. were involved in the additional hydrolysis of the peptide mixtures. The degree of hydrolysis (DH, total phenolic contents, and protein contents of these hydrolysates were as follows: DH (about 20–28%, total phenolics (15.3–27.2 μg/mg sample powder, and proteins (162.7–242.8 μg/mg sample powder, respectively. The hydrolysates possessed high antiradical scavenging activity determined with DPPH (42–46% inhibition. The prepared hydrolysates of bee-collected flower pollen may be regarded as effective natural and functional dietary food supplements due to their remarkable content of polyphenol substances and significant radical-scavenging capacity with special regard to their nutritional-physiological implications.

Careful Determination of Inservice Inspection of piping by Computer Analysis in Nuclear Power Plant

International Nuclear Information System (INIS)

Lim, H. T.; Lee, S. L.; Lee, J. P.; Kim, B. C.

1992-01-01

Stress analysis has been performed using computer program ANSYS in the pressurizer surge line in accordance with ASME Sec. III in order to predict possibility of fatigue failure due to thermal stratification phenomena in pipes connected to reactor coolant system of nuclear power plants. Highly vulnerable area to crack generation has been chosen by the analysis of fatigue due to thermal stress in pressurizer surge line. This kind of result can be helpful to choose the location requiring intensive care during inservice inspection of nuclear power plants

Integration of Computational and Preparative Techniques to Demonstrate Physical Organic Concepts in Synthetic Organic Chemistry: An Example Using Diels-Alder Reaction

Science.gov (United States)

Palmer, David R. J.

2004-01-01

The Diels-Alder reaction is used as an example for showing the integration of computational and preparative techniques, which help in demonstrating the physical organic concepts in synthetic organic chemistry. These experiments show that the students should not accept the computational results without questioning them and in many Diels-Alder…

Colour and toxic characteristics of metakaolinite–hematite pigment for integrally coloured concrete, prepared from iron oxide recovered from a water treatment plant of an abandoned coal mine

International Nuclear Information System (INIS)

Sadasivam, Sivachidambaram; Thomas, Hywel Rhys

2016-01-01

A metakaolinite-hematite (KH) red pigment was prepared using an ocherous iron oxide sludge recovered from a water treatment plant of an abandoned coal mine. The KH pigment was prepared by heating the kaolinite and the iron oxide sludge at kaolinite's dehydroxylation temperature. Both the raw sludge and the KH specimen were characterised for their colour properties and toxic characteristics. The KH specimen could serve as a pigment for integrally coloured concrete and offers a potential use for the large volumes of the iron oxide sludge collected from mine water treatment plants. - Graphical abstract: A kaolinite based red pigment was prepared using an ocherous iron oxide sludge recovered from an abandoned coal mine water treatment plant. Display Omitted - Highlights: • A red pigment was prepared by heating a kaolinite and an iron oxide sludge. • The iron oxide and the pigment were characterised for their colour properties. • The red pigment can be a potential element for integrally coloured concrete.

Guided access cavity preparation using cone-beam computed tomography and optical surface scans - an ex vivo study

DEFF Research Database (Denmark)

Buchgreitz, J; Buchgreitz, M; Mortensen, D

2016-01-01

AIM: To evaluate ex vivo, the accuracy of a preparation procedure planned for teeth with pulp canal obliteration (PCO) using a guide rail concept based on a cone-beam computed tomography (CBCT) scan merged with an optical surface scan. METHODOLOGY: A total of 48 teeth were mounted in acrylic bloc...

Adsorption of caffeine on mesoporous activated carbon fibers prepared from pineapple plant leaves.

Science.gov (United States)

Beltrame, Karla K; Cazetta, André L; de Souza, Patrícia S C; Spessato, Lucas; Silva, Taís L; Almeida, Vitor C

2018-01-01

The present work reports the preparation of activated carbon fibers (ACFs) from pineapple plant leaves, and its application on caffeine (CFN) removal from aqueous solution. The preparation procedure was carried out using the H 3 PO 4 as activating agent and slow pyrolysis under N 2 atmosphere. The characterization of materials was performed from the N 2 adsorption and desorption isotherms, scanning electron microscopy (SEM), thermogravimetric analysis (TGA), Fourier transform infrared spectroscopy (FTIR), X-ray diffraction (XRD), Raman spectroscopy, Boehm titration and pH pzc method. ACFs showed high BET surface area value (S BET = 1031m 2 g -1 ), well-developed mesoporous structure (mesopore volume of 1.27cm³ g -1 ) and pores with average diameter (D M ) of 5.87nm. Additionally, ACFs showed features of fibrous material with predominance of acid groups on its surface. Adsorption studies indicated that the pseudo-second order kinetic and Langmuir isotherm models were that best fitted to the experimental data. The monolayer adsorption capacity was found to be 155.50mgg -1 . thermodynamic studies revealed that adsorption process is spontaneous, exothermic and occurs preferably via physisorption. The pineapple leaves are an efficient precursor for preparation of ACFs, which were successful applied as adsorbent material for removal of caffeine from the aqueous solutions. Copyright © 2017 Elsevier Inc. All rights reserved.

Plant simulator

International Nuclear Information System (INIS)

Fukumitsu, Hiroyuki

1998-01-01

A simulator of a reactor plant of the present invention comprises a plurality of distributed computers, an indication processing section and an operation section. The simulation calculation functions of various kinds of plant models in the plant are shared by the plurality of computers. The indication processing section controls collection of data of the plant simulated by the computers and instructions of an operator. The operation section is operated by the operator and the results of operation are transmitted to the indication processing section, to conduct operation trainings and display the results of the simulation. Each of the computers and the indication processing portion are connected with each other by a network having a memory for common use. Data such as the results of calculation of plant models and various kinds of parameters of the plant required commonly to the calculators and the indication processing section are stored in the common memory, and adapted to be used by way of the network. (N.H.)

Piping information centralized management system for nuclear plant, PIMAS

International Nuclear Information System (INIS)

Matsumoto, Masaru

1977-01-01

Piping works frequently cause many troubles in the progress of construction works, because piping is the final procedure in design and construction and is forced to suffer the problems in earlier stages. The enormous amount of data on quality control and management leads to the employment of many unskilled designers of low technical ability, and it causes confusion in installation and inspection works. In order to improve the situation, the ''piping information management system for nuclear plants (PIMAS)'' has been introduced attempting labor-saving and speed-up. Its main purposes are the mechanization of drafting works, the centralization of piping informations, labor-saving and speed-up in preparing production control data and material management. The features of the system are as follows: anyone can use the same informations whenever he requires them because the informations handled in design works are contained in a large computer; the system can be operated on-line, and the terminals are provided in the sections which require informations; and the sub-systems are completed for preparing a variety of drawings and data. Through the system, material control has become possible by using the material data in each plant, stock material data and the information on the revision of drawings in the design department. Efficiency improvement and information centralization in the manufacturing department have also been achieved because the computer has prepared many kinds of slips based on unified drawings and accurate informations. (Wakatsuki, Y.)

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...

MODEL OF THE IMPLEMENTATION PROCESS OF DESIGNING A CLOUD-BASED LEARNING ENVIRONMENT FOR THE PREPARATION OF BACHELOR OF COMPUTER SCIENCE

Directory of Open Access Journals (Sweden)

Vakaliuk T.

2017-12-01

Full Text Available The article presents the model of the process of implementation of the design of a cloud-oriented learning environment (CBLE for the preparation of bachelor of computer science, which consists of seven stages: analysis, setting goals and objectives, formulating requirements for the cloud-oriented learning environment, modeling the CBLE, developing CBLE, using CBLE in the educational Bachelor of Computer Science and Performance Testing. Each stage contains sub-steps. The analysis stage is considered in three aspects: psychological, pedagogical and technological. The formulation of the requirements for the CBLE was carried out taking into account the content and objectives of the training; experience of using CBLE; the personal qualities and knowledge, skills and abilities of students. The simulation phase was divided into sub-stages: the development of a structural and functional model of the CBLE for the preparation of bachelors of computer science; development of a model of cloud-oriented learning support system (COLSS; development of a model of interaction processes in CBLE. The fifth stage was also divided into the following sub-steps: domain registration and customization of the appearance of COLSS; definition of the disciplines provided by the curriculum preparation of bachelors of computer science; creation of own cabinets of teachers and students; download educational and methodological and accompanying materials; the choice of traditional and cloud-oriented forms, methods, means of training. The verification of the functioning of the CBLE will be carried out in the following areas: the functioning of the CBLE; results of students' educational activity; formation of information and communication competence of students.

Development of processing procedure preparing for digital computer controlled equipment on modular design base

International Nuclear Information System (INIS)

Starosel'tsev, O.P.; Khrundin, V.I.

1982-01-01

In order to reduce labour consumption of technological preparation of production for digital computer controlled machines during the treatment of steam turbines articles created is a system of modular design of technological processes and controlling programs. A set of typical modulas-transitions, being a number of surfaces of an articles treated with one cutting tool in optimum sequence, and a library of cutting tools are the base of the system. Introduction of such a system sharply enhaneces the efficiency of the equipment utilization [ru

Online Monitoring and Controlling Water Plant System Based on IoT Cloud Computing and Arduino

Directory of Open Access Journals (Sweden)

Ali Najim Abdullah

2017-07-01

Full Text Available Water is basis of the existence of life on earth and its invaluable because it’s an essential requirement for all the human beings but, presently water preparation and processing systems are suffering from different problems such as real-time operations problems, loss of large amounts of water in the liquidation and distribution operations, less amount of water sources, i.e. The increase in water problems coincides with the increase in population numbers and residential areas such as (water distribution, consumption, Interrupted water sources problems as well as water quality. Therefore, to eliminate these problems and make more efficient water systems, effective and reliable there is necessity for accurate monitoring and proper controlling system. In this paper, we are focusing on the design of water system in real-time and on the continuous monitoring of water based on IoT cloud computing and Arduino microcontroller. Water system with proper control algorithm and continuous monitoring any place and any time makes a stable distribution so that, we can have a record of height of water in tanks and we can change the devices status in the plant. Internet of things is a network of physical connected objects equipped with software, electronics circuits, sensors, and network connection part which allow monitoring and controlling anywhere around the world. Through using cloud computing proved by free severs, the water system’s data continuously is uploaded to cloud allowing the real time monitoring operation by the use of sensors and microcontroller (Arduino as Minicomputer to control and monitor the system operation from cloud with efficient (client to server connection.

The profesional preparation of the tutors to atten d the midle level technical in electrotec hnical and Computer in job training

Directory of Open Access Journals (Sweden)

Melba Rivas Cáceres

2015-09-01

Full Text Available The article is about a study of the preparation of the tutors o f the technicians of Electrotechnics and Computer science in labor training. In this one reflects about histor ic antecedent and tendencies in the preparation of the tutors of the labor entities, about the stage of labor training and the rols of the tutor i n the labor entities in the attention of the one trained , as well as the theoretical sustenance of the process of the tutors' preparation.

Real-time computing in environmental monitoring of a nuclear power plant

International Nuclear Information System (INIS)

Deme, S.; Lang, E.; Nagy, Gy.

1987-06-01

A real-time computing method is described for calculating the environmental radiation exposure due to a nuclear power plant both at normal operation and at accident. The effects of the Gaussian plume are recalculated in every ten minutes based on meteorological parameters measured at a height of 20 and 120 m as well as on emission data. At normal operation the quantity of radioactive materials released through the stacks is measured and registered while, at an accident, the source strength is unknown and the calculated relative data are normalized to the values measured at the eight environmental monitoring stations. The doses due to noble gases and to dry and wet deposition as well as the time integral of 131 I concentration are calculated and stored by a professional personal computer for 720 points of the environment of 11 km radius. (author)

Quality assurance program preparation - review of requirements and plant systems - selection of program levels

International Nuclear Information System (INIS)

Asmuss, G.

1980-01-01

The establishment and implementation for a practicable quality assurance program for a nuclear power plant demands a detailed background in the field of engineering, manufacturing, organization and quality assurance. It will be demonstrated with examples to define and control the achievement of quality related activities during the phases of design, procurement, manufactoring, commissioning and operation. In general the quality assurance program applies to all items, processes and services important to safety of nuclear power plant. The classification for safety related and non-safety related items and services demonstrate the levels of quality assurance requirements. The lecture gives an introduction of QA Program preparation under the following topics: -Basic criteria and international requirements - Interaction of QA activities - Modular and product oriented QA programs - Structuring of organization for the QA program - Identification of the main quality assurance functions and required actions - Quality Assurance Program documentation - Documentation of planning of activities - Control of program documents - Definitions. (orig./RW)

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

Computational models for residual creep life prediction of power plant components

International Nuclear Information System (INIS)

Grewal, G.S.; Singh, A.K.; Ramamoortry, M.

2006-01-01

All high temperature - high pressure power plant components are prone to irreversible visco-plastic deformation by the phenomenon of creep. The steady state creep response as well as the total creep life of a material is related to the operational component temperature through, respectively, the exponential and inverse exponential relationships. Minor increases in the component temperature can thus have serious consequences as far as the creep life and dimensional stability of a plant component are concerned. In high temperature steam tubing in power plants, one mechanism by which a significant temperature rise can occur is by the growth of a thermally insulating oxide film on its steam side surface. In the present paper, an elegantly simple and computationally efficient technique is presented for predicting the residual creep life of steel components subjected to continual steam side oxide film growth. Similarly, fabrication of high temperature power plant components involves extensive use of welding as the fabrication process of choice. Naturally, issues related to the creep life of weldments have to be seriously addressed for safe and continual operation of the welded plant component. Unfortunately, a typical weldment in an engineering structure is a zone of complex microstructural gradation comprising of a number of distinct sub-zones with distinct meso-scale and micro-scale morphology of the phases and (even) chemistry and its creep life prediction presents considerable challenges. The present paper presents a stochastic algorithm, which can be' used for developing experimental creep-cavitation intensity versus residual life correlations for welded structures. Apart from estimates of the residual life in a mean field sense, the model can be used for predicting the reliability of the plant component in a rigorous probabilistic setting. (author)

Convincing Conversations : Using a Computer-Based Dialogue System to Promote a Plant-Based Diet

NARCIS (Netherlands)

Zaal, Emma; Mills, Gregory; Hagen, Afke; Huisman, Carlijn; Hoeks, Jacobus

2017-01-01

In this study, we tested the effectiveness of a computer-based persuasive dialogue system designed to promote a plant-based diet. The production and consumption of meat and dairy has been shown to be a major cause of climate change and a threat to public health, bio-diversity, animal rights and

Review of P-scan computer-based ultrasonic inservice inspection system. Supplement 1

International Nuclear Information System (INIS)

Harris, R.V. Jr.; Angel, L.J.

1995-12-01

This Supplement reviews the P-scan system, a computer-based ultrasonic system used for inservice inspection of piping and other components in nuclear power plants. The Supplement was prepared using the methodology described in detail in Appendix A of NUREG/CR-5985, and is based on one month of using the system in a laboratory. This Supplement describes and characterizes: computer system, ultrasonic components, and mechanical components; scanning, detection, digitizing, imaging, data interpretation, operator interaction, data handling, and record-keeping. It includes a general description, a review checklist, and detailed results of all tests performed

Confirmation of the seismic resistance of nuclear power plant equipment after assembly

International Nuclear Information System (INIS)

Kaznovsky, P. S.; Kaznovsky, A. P.; Saakov, E. S.; Ryasnyj, S. I.

2013-01-01

It is shown that the natural frequencies and damping decrements of nuclear power plant equipment can only be determined experimentally and directly at the power generation units (reactors) of nuclear power plants under real disassembly conditions for the equipment, piping network, thermal insulation, etc. A computational experimental method is described in which the natural frequencies and damping decrements are determined in the field and the seismic resistance is reevaluated using these values. This method is the basis of the standards document “Methods for confirming the dynamic characteristics of systems and components of the generating units of nuclear power plants which are important for safety” prepared and introduced in 2012.

Computer-aided load monitoring system for nuclear power plant steel framing structures

International Nuclear Information System (INIS)

Skaczylo, A.T.; Fung, S-J; Hooks, R.W.

1984-01-01

The design of nuclear power plant steel framing structures is a long and involved process. It is often complicated by numerous changes in design loads as a result of additions, deletions and modifications of HVAC hangers, cable tray hangers, electric conduit hangers, and small bore and large bore mechanical component supports. Manual tracking of load changes of thousands of supports and their impact to the structural steel design adequacy is very time-consuming and is susceptible to errors. This paper presents a computer-aided load monitoring system using the latest technology of data base management and interactive computer software. By linking the data base to analysis and investigation computer programs, the engineer has a very powerful tool to monitor not only the load revisions but also their impact on the steel structural floor framing members and connections. Links to reporting programs allow quick information retrieval in the form of comprehensive reports. Drawing programs extract data from the data base to draw hanger load system drawings on a computer-aided drafting system. These capabilities allow engineers to minimize modifications by strategically locating new hangers or rearranging auxiliary steel configuration

A Study on Soft Computing Applications in I and C Systems of Nuclear Power Plant

International Nuclear Information System (INIS)

Kang, H. T.; Chung, H. Y.

2006-01-01

In the paper, the application of the soft computing based nuclear power plant(NPP) is discussed. Soft computing such as neural network(NN), fuzzy logic controller(FLC), and genetic algorithm(GA) and/or their hybrid will be a new frontier for the development of instrument and control(I and C) systems in NPP. The application includes several fields, for example, the diagnostics of system transient, optimal data selection in NN, and intelligent control etc. Two or more combining structure, hybrid system, is more efficient. The concept of FLC, NN, and GA is presented in Section 2. The applications of soft computing used in NPP are presented in Section 3

A study on the optimal replacement periods of digital control computer's components of Wolsung nuclear power plant unit 1

International Nuclear Information System (INIS)

Mok, Jin Il; Seong, Poong Hyun

1993-01-01

Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Even a trip of a single nuclear power plant (NPP) causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this paper we investigated the optimal replacement periods of the control computer's components of Wolsung nuclear power plant Unit 1. We first derived mathematical models of optimal replacement periods to the digital control computer's components of Wolsung NPP Unit 1 and calculated the optimal replacement periods analytically. We compared the periods with the replacement periods currently used at Wolsung NPP Unit 1. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained and those used in the field show a little difference. (Author)

The manual of a computer software 'FBR Plant Planning Design Prototype System'

International Nuclear Information System (INIS)

2003-10-01

This is a manual of a computer software 'FBR Plant Planning Design Prototype System', which enables users to conduct case studies of deviated FBR design concepts based on 'MONJU'. The calculations simply proceed as the user clicks displayed buttons, therefore step-by-step explanation is supposed not be necessary. The following pages introduce only particular features of this software, i.e, each interactive screens, functions of buttons and consequences after clicks, and the quitting procedure. (author)

Fiscal 1995 survey report on the environmentally friendly type coal utilization system joint demonstration project. Water-saving coal preparation system joint demonstration project; Kankyo chowagata sekitan riyo system kyodo jissho jigyo. Shosuigata sentan system kyodo jissho jigyo

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

This project makes demonstration of clean coal technology (CCT) in China and preparation for the base of its spread, controlled environmental pollution due to the coal use by the countries concerned, and contributes to stably secure energy of Japan. The paper made analog operation in the 1960s-1970s, supported by Russia and Poland, introduced two computer systems for operational control and quality control, densimeter, level meter, flow meter and analyzer to coal preparation plants having problems on productivity and quality control, made the optimum operational diagnosis for the plants, and at the same time, demonstrated the comprehensive rehabilitation type system by which water saving, high quality and high effectiveness are obtained. Various types of sensors such as rapid ash meter, scale and densitometer and computers are introduced to coal preparation plants which were recently constructed in China, have jig or heavy liquid cyclone as main preparation equipment and conducts operational control. There, the central control system was demonstrated in which various information collected in the central operation room and in-site equipment is combined by network for high-grade data processing and water saving is achieved. 50 figs., 11 tabs.

Adverse effects of plant food supplements and botanical preparations: a systematic review with critical evaluation of causality.

Science.gov (United States)

Di Lorenzo, Chiara; Ceschi, Alessandro; Kupferschmidt, Hugo; Lüde, Saskia; De Souza Nascimento, Elizabeth; Dos Santos, Ariana; Colombo, Francesca; Frigerio, Gianfranco; Nørby, Karin; Plumb, Jenny; Finglas, Paul; Restani, Patrizia

2015-04-01

The objective of this review was to collect available data on the following: (i) adverse effects observed in humans from the intake of plant food supplements or botanical preparations; (ii) the misidentification of poisonous plants; and (iii) interactions between plant food supplements/botanicals and conventional drugs or nutrients. PubMed/MEDLINE and Embase were searched from database inception to June 2014, using the terms 'adverse effect/s', 'poisoning/s', 'plant food supplement/s', 'misidentification/s' and 'interaction/s' in combination with the relevant plant name. All papers were critically evaluated according to the World Health Organization Guidelines for causality assessment. Data were obtained for 66 plants that are common ingredients of plant food supplements; of the 492 papers selected, 402 (81.7%) dealt with adverse effects directly associated with the botanical and 89 (18.1%) concerned interactions with conventional drugs. Only one case was associated with misidentification. Adverse effects were reported for 39 of the 66 botanical substances searched. Of the total references, 86.6% were associated with 14 plants, including Glycine max/soybean (19.3%), Glycyrrhiza glabra/liquorice (12.2%), Camellia sinensis/green tea ( 8.7%) and Ginkgo biloba/gingko (8.5%). Considering the length of time examined and the number of plants included in the review, it is remarkable that: (i) the adverse effects due to botanical ingredients were relatively infrequent, if assessed for causality; and (ii) the number of severe clinical reactions was very limited, but some fatal cases have been described. Data presented in this review were assessed for quality in order to make the results maximally useful for clinicians in identifying or excluding deleterious effects of botanicals. © 2014 The British Pharmacological Society.

Computer-based system for inspection of water chemistry regimes in WWER-type nuclear power plants

International Nuclear Information System (INIS)

Burcl, R.; Novak, M.; Malenka, P.

1993-01-01

The unsatisfactory situation in water chemistry testing at nuclear power plants with WWER type reactors is described. The testing primarily relies on laboratory analyses of manually taken samples. About 40 samples from one unit are tested per shift, which comprises approximately 250 determinations of various parameters. The time between two determinations is no shorter than 4 to 6 hours, thus rapid parameter changes between two determinations fail to be monitored. A novel system of automated chemistry monitoring is outlined, feasible for WWER type reactors. The system comprises 10 sets of sensors for monitoring all the relevant chemistry parameters of both the primary and secondary coolant circuits. Each sensor set has its own autonomous computer which secures its function even in case of loss of the chemical information network. The entire system is controlled by a master computer which also collects the results and provides contact with the power plant's information system. (Z.S.). 1 fig

Computer group

International Nuclear Information System (INIS)

Bauer, H.; Black, I.; Heusler, A.; Hoeptner, G.; Krafft, F.; Lang, R.; Moellenkamp, R.; Mueller, W.; Mueller, W.F.; Schati, C.; Schmidt, A.; Schwind, D.; Weber, G.

1983-01-01

The computer groups has been reorganized to take charge for the general purpose computers DEC10 and VAX and the computer network (Dataswitch, DECnet, IBM - connections to GSI and IPP, preparation for Datex-P). (orig.)

The effects of compost prepared from waste material of banana plants on the nutrient contents of banana leaves.

Science.gov (United States)

Doran, Ilhan; Sen, Bahtiyar; Kaya, Zülküf

2003-10-01

In this study, the possible utilization of removed shoots and plant parts of banana as compost after fruit harvest were investigated. Three doses (15-30-45 kg plan(-1)) of the compost prepared from the clone of Dwarf Cavendish banana were compared with Farmyard manure (50 kg plant(-1), Mineral fertilizers (180 g N + 150 g P + 335 g K plant(-1)) and Farmyard manure + Mineral fertilizers (25 kg FM + 180 g N + 150 g P + 335 g K plant(-1)) which determined positive effects on the nutrient contents of banana leaves. The banana plants were grown under a heated glasshouse and in a soil with physical and chemical properties suitable for banana growing. The contents of N, P, K and Mg in compost and in farmyard manure were found to be similar. Nitrogen, phosphorus and potassium contents of leaves in all applications except control, and Ca, Mg, Fe, Zn, Mn, Cu contents in all applications were determined between optimum levels of reference values. There were positive correlations among some nutrient contents of leaves, growth, yield and fruit quality characteristics. Farmyard manure, Farmyard manure + Mineral fertilizers and 45 kg plant(-1) of compost increased the nutrient contents of banana leaves. According to obtained results, 45 kg plant(-1) of compost was determined more suitable in terms of economical production and organic farming than the other fertiliser types.

Efficient preparation of large-block-code ancilla states for fault-tolerant quantum computation

Science.gov (United States)

Zheng, Yi-Cong; Lai, Ching-Yi; Brun, Todd A.

2018-03-01

Fault-tolerant quantum computation (FTQC) schemes that use multiqubit large block codes can potentially reduce the resource overhead to a great extent. A major obstacle is the requirement for a large number of clean ancilla states of different types without correlated errors inside each block. These ancilla states are usually logical stabilizer states of the data-code blocks, which are generally difficult to prepare if the code size is large. Previously, we have proposed an ancilla distillation protocol for Calderbank-Shor-Steane (CSS) codes by classical error-correcting codes. It was assumed that the quantum gates in the distillation circuit were perfect; however, in reality, noisy quantum gates may introduce correlated errors that are not treatable by the protocol. In this paper, we show that additional postselection by another classical error-detecting code can be applied to remove almost all correlated errors. Consequently, the revised protocol is fully fault tolerant and capable of preparing a large set of stabilizer states sufficient for FTQC using large block codes. At the same time, the yield rate can be boosted from O (t-2) to O (1 ) in practice for an [[n ,k ,d =2 t +1

Introduction and preparation of the nuclear fuel cycle facility risk analysis code: STAR

International Nuclear Information System (INIS)

Nomura, Yasushi

1990-09-01

STAR code is a computer program, by which one can perform the probabilistic safety assessment (PSA) for the nuclear fuel cycle facility in both the normal and the accidental event of environmental radioactive material release. This code was originally developed by NUKEM GmbH in West Germany as a fruit of the PSE (Projekt Sicherheitsstudien Entsorgung) aiming at R and D of safety analysis methods for use in nuclear fuel cycle facilities such as reprocessing plants. In JAERI, efforts have been made to research and develop safety assessment methods applicable to the accidental situations assumed to happen in the reprocessing plants. In this line of objectives, the STAR code was introduced from NUKEM GmbH in 1986 and, since then, has been improved and prepared to add an ability to analyze public radiation exposure by released activities from the plants. At the first stage of this code preparation, the program conversion was made to adapt the STAR code, originally operative on IBM-compatible PC's and Hewlett Packard 7550A plotters, to NEC PC 9801RX and NEC PR 602R page printers installed in the Fuel Cycle Safety Assessment Laboratory of JAERI. This report describes calculational performances of the STAR code, results of the improvement and preparation works together with input/output data format in illustration of a sample HALW (High Activity Liquid Waste) tank PSA problem, thus making a users' manual for the STAR code. (author)

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.

Computer modelling of the combined effects of plant conditions and coal quality on burnout in utility furnaces

Energy Technology Data Exchange (ETDEWEB)

P. Stephenson [RWE npower Engineering, Swindon (United Kingdom)

2007-09-15

The aim of this paper is to describe the latest steps in the development of a computer model to predict the combined effects of plant conditions and coal quality on burnout. The work was conducted as part of RWE's contribution to the recent ECSC project 'Development of a carbon-in-ash notification system (CARNO)'. A burnout predictor code has been developed and validated; it includes both coal and plant effects and includes a burnout model based closely on CBK8. The agreement between predicted C-in-ash and plant data is encouraging, but further improvements are still desirable. The predictions obtained from the burnout predictor show that the calculated sensitivities to changes in plant condition can be very dependent on state of plant. 7 refs., 7 figs., 1 tab.

The modernization of the process computer of the Trillo Nuclear Power Plant; Modernizacion del ordenador de proceso de la Central Nuclear de Trillo

Energy Technology Data Exchange (ETDEWEB)

Martin Aparicio, J.; Atanasio, J.

2011-07-01

The paper describes the modernization of the Process computer of the Trillo Nuclear Power Plant. The process computer functions, have been incorporated in the non Safety I and C platform selected in Trillo NPP: the Siemens SPPA-T2000 OM690 (formerly known as Teleperm XP). The upgrade of the Human Machine Interface of the control room has been included in the project. The modernization project has followed the same development process used in the upgrade of the process computer of PWR German nuclear power plants. (Author)

The iPlant Collaborative: Cyberinfrastructure for Plant Biology

Science.gov (United States)

Goff, Stephen A.; Vaughn, Matthew; McKay, Sheldon; Lyons, Eric; Stapleton, Ann E.; Gessler, Damian; Matasci, Naim; Wang, Liya; Hanlon, Matthew; Lenards, Andrew; Muir, Andy; Merchant, Nirav; Lowry, Sonya; Mock, Stephen; Helmke, Matthew; Kubach, Adam; Narro, Martha; Hopkins, Nicole; Micklos, David; Hilgert, Uwe; Gonzales, Michael; Jordan, Chris; Skidmore, Edwin; Dooley, Rion; Cazes, John; McLay, Robert; Lu, Zhenyuan; Pasternak, Shiran; Koesterke, Lars; Piel, William H.; Grene, Ruth; Noutsos, Christos; Gendler, Karla; Feng, Xin; Tang, Chunlao; Lent, Monica; Kim, Seung-Jin; Kvilekval, Kristian; Manjunath, B. S.; Tannen, Val; Stamatakis, Alexandros; Sanderson, Michael; Welch, Stephen M.; Cranston, Karen A.; Soltis, Pamela; Soltis, Doug; O'Meara, Brian; Ane, Cecile; Brutnell, Tom; Kleibenstein, Daniel J.; White, Jeffery W.; Leebens-Mack, James; Donoghue, Michael J.; Spalding, Edgar P.; Vision, Todd J.; Myers, Christopher R.; Lowenthal, David; Enquist, Brian J.; Boyle, Brad; Akoglu, Ali; Andrews, Greg; Ram, Sudha; Ware, Doreen; Stein, Lincoln; Stanzione, Dan

2011-01-01

The iPlant Collaborative (iPlant) is a United States National Science Foundation (NSF) funded project that aims to create an innovative, comprehensive, and foundational cyberinfrastructure in support of plant biology research (PSCIC, 2006). iPlant is developing cyberinfrastructure that uniquely enables scientists throughout the diverse fields that comprise plant biology to address Grand Challenges in new ways, to stimulate and facilitate cross-disciplinary research, to promote biology and computer science research interactions, and to train the next generation of scientists on the use of cyberinfrastructure in research and education. Meeting humanity's projected demands for agricultural and forest products and the expectation that natural ecosystems be managed sustainably will require synergies from the application of information technologies. The iPlant cyberinfrastructure design is based on an unprecedented period of research community input, and leverages developments in high-performance computing, data storage, and cyberinfrastructure for the physical sciences. iPlant is an open-source project with application programming interfaces that allow the community to extend the infrastructure to meet its needs. iPlant is sponsoring community-driven workshops addressing specific scientific questions via analysis tool integration and hypothesis testing. These workshops teach researchers how to add bioinformatics tools and/or datasets into the iPlant cyberinfrastructure enabling plant scientists to perform complex analyses on large datasets without the need to master the command-line or high-performance computational services. PMID:22645531

The iPlant Collaborative: Cyberinfrastructure for Plant Biology.

Science.gov (United States)

Goff, Stephen A; Vaughn, Matthew; McKay, Sheldon; Lyons, Eric; Stapleton, Ann E; Gessler, Damian; Matasci, Naim; Wang, Liya; Hanlon, Matthew; Lenards, Andrew; Muir, Andy; Merchant, Nirav; Lowry, Sonya; Mock, Stephen; Helmke, Matthew; Kubach, Adam; Narro, Martha; Hopkins, Nicole; Micklos, David; Hilgert, Uwe; Gonzales, Michael; Jordan, Chris; Skidmore, Edwin; Dooley, Rion; Cazes, John; McLay, Robert; Lu, Zhenyuan; Pasternak, Shiran; Koesterke, Lars; Piel, William H; Grene, Ruth; Noutsos, Christos; Gendler, Karla; Feng, Xin; Tang, Chunlao; Lent, Monica; Kim, Seung-Jin; Kvilekval, Kristian; Manjunath, B S; Tannen, Val; Stamatakis, Alexandros; Sanderson, Michael; Welch, Stephen M; Cranston, Karen A; Soltis, Pamela; Soltis, Doug; O'Meara, Brian; Ane, Cecile; Brutnell, Tom; Kleibenstein, Daniel J; White, Jeffery W; Leebens-Mack, James; Donoghue, Michael J; Spalding, Edgar P; Vision, Todd J; Myers, Christopher R; Lowenthal, David; Enquist, Brian J; Boyle, Brad; Akoglu, Ali; Andrews, Greg; Ram, Sudha; Ware, Doreen; Stein, Lincoln; Stanzione, Dan

2011-01-01

The iPlant Collaborative (iPlant) is a United States National Science Foundation (NSF) funded project that aims to create an innovative, comprehensive, and foundational cyberinfrastructure in support of plant biology research (PSCIC, 2006). iPlant is developing cyberinfrastructure that uniquely enables scientists throughout the diverse fields that comprise plant biology to address Grand Challenges in new ways, to stimulate and facilitate cross-disciplinary research, to promote biology and computer science research interactions, and to train the next generation of scientists on the use of cyberinfrastructure in research and education. Meeting humanity's projected demands for agricultural and forest products and the expectation that natural ecosystems be managed sustainably will require synergies from the application of information technologies. The iPlant cyberinfrastructure design is based on an unprecedented period of research community input, and leverages developments in high-performance computing, data storage, and cyberinfrastructure for the physical sciences. iPlant is an open-source project with application programming interfaces that allow the community to extend the infrastructure to meet its needs. iPlant is sponsoring community-driven workshops addressing specific scientific questions via analysis tool integration and hypothesis testing. These workshops teach researchers how to add bioinformatics tools and/or datasets into the iPlant cyberinfrastructure enabling plant scientists to perform complex analyses on large datasets without the need to master the command-line or high-performance computational services.

The iPlant Collaborative: Cyberinfrastructure for Plant Biology

Directory of Open Access Journals (Sweden)

Stephen A Goff

2011-07-01

Full Text Available The iPlant Collaborative (iPlant is a United States National Science Foundation (NSF funded project that aims to create an innovative, comprehensive, and foundational cyberinfrastructure in support of plant biology research (PSCIC, 2006. iPlant is developing cyberinfrastructure that uniquely enables scientists throughout the diverse fields that comprise plant biology to address Grand Challenges in new ways, to stimulate and facilitate cross-disciplinary research, to promote biology and computer science research interactions, and to train the next generation of scientists on the use of cyberinfrastructure in research and education. Meeting humanity's projected demands for agricultural and forest products and the expectation that natural ecosystems be managed sustainably will require synergies from the application of information technologies. The iPlant cyberinfrastructure design is based on an unprecedented period of research community input, and leverages developments in high-performance computing, data storage, and cyberinfrastructure for the physical sciences. iPlant is an open-source project with application programming interfaces that allow the community to extend the infrastructure to meet its needs. iPlant is sponsoring community-driven workshops addressing specific scientific questions via analysis tool integration and hypothesis testing. These workshops teach researchers how to add bioinformatics tools and/or datasets into the iPlant cyberinfrastructure enabling plant scientists to perform complex analyses on large datasets without the need to master the command-line or high-performance computational services.

A summary report on feed preparation offgas and glass redox data for Hanford waste vitrification plant: Letter report

International Nuclear Information System (INIS)

Merz, M.D.

1996-03-01

Tests to evaluate feed processing options for the Hanford Waste Vitrification Plant (HWVP) were conducted by a number of investigators, and considerable data were acquired for tests of different scale, including recent full-scale tests. In this report, a comparison was made of the characteristics of feed preparation observed in tests of scale ranging from 57 ml to full-scale of 28,000 liters. These tests included Pacific Northwest Laboratory (PNL) laboratory-scale tests, Kernforschungszentrums Karlsruhe (KfK) melter feed preparation, Research Scale Melter (RSM) feed preparation, Integrated DWPF Melter System (IDMS) feed preparation, Slurry Integrated Performance Testing (SIPT) feed preparation, and formic acid addition to Hanford Neutralized Current Acid Waste (NCAW) care samples.' The data presented herein were drawn mainly from draft reports and include system characteristics such as slurry volume and depth, sweep gas flow rate, headspace, and heating and stirring characteristics. Operating conditions such as acid feed rate, temperature, starting pH, final pH, quantities and type of frit, nitrite, nitrate, and carbonate concentrations, noble metal content, and waste oxide loading were tabulated. Offgas data for CO 2 , NO x , N 2 O, NO 2 , H 2 and NH 3 were tabulated on a common basis. Observation and non-observation of other species were also noted

Site preparation works for No.3 plant in Ikata Nuclear Power Station, Shikoku Electric Power Co., Inc

International Nuclear Information System (INIS)

Ishihara, Hisashi; Nakajima, Hiroshi; Oshima, Teruhiko

1986-01-01

Ikata Power Station is only nuclear power station in Shikoku located at the root of Sadamisaki Peninsula. No.1 plant started the operation in September, 1977, and No.2 plant started the operation in March, 1982. By constructing No.3 plant of 890 MWe output, the total power output will be 2.022 million kW. No.3 plant is installed adjacently to No.1 and No.2 plants on their east side. In this place, the existing facilities of the harbor and others can be effectively utilized, the nature of ground is solid, and the fundamental condition of location is perfect, it is easy to obtain the cooperation of local people as No.1 and No.2 plants have been in operation, and it is advantageous in view of the construction period for the power supply plan. The site preparation works have progressed smoothly since the start in June, 1985. About 100,000 m 2 of the site is created by cutting natural ground, and about 54,000 m 2 is created by sea reclamation. About 5 million m 3 of earth and stone generated by cutting and excavation are utilized for reclamation, revetment and others. The topographic and geological features, sea condition, the outline of geological survey, the layout, and the construction works of revetment, cutting, the creation of substitute seaweed farm, appurtenant works, and the measures for environment preservation are described. (Kako, I.)

PlantCV v2: Image analysis software for high-throughput plant phenotyping

Directory of Open Access Journals (Sweden)

Malia A. Gehan

2017-12-01

Full Text Available Systems for collecting image data in conjunction with computer vision techniques are a powerful tool for increasing the temporal resolution at which plant phenotypes can be measured non-destructively. Computational tools that are flexible and extendable are needed to address the diversity of plant phenotyping problems. We previously described the Plant Computer Vision (PlantCV software package, which is an image processing toolkit for plant phenotyping analysis. The goal of the PlantCV project is to develop a set of modular, reusable, and repurposable tools for plant image analysis that are open-source and community-developed. Here we present the details and rationale for major developments in the second major release of PlantCV. In addition to overall improvements in the organization of the PlantCV project, new functionality includes a set of new image processing and normalization tools, support for analyzing images that include multiple plants, leaf segmentation, landmark identification tools for morphometrics, and modules for machine learning.

Limited effectiveness of over-the-counter plant preparations used for the treatment of urinary tract infections as inhibitors of the urease activity from Staphylococcus saprophyticus.

Science.gov (United States)

Deutch, C E

2017-05-01

Urease is a key virulence factor for the Gram-positive urinary tract pathogen Staphylococcus saprophyticus and a potential target for antimicrobial therapy. The enzyme from S. saprophyticus is unusual in that it does not contain cysteine at the active site. The aims of this study were to test 14 over-the-counter plant preparations as inhibitors of this urease and to determine whether they can prevent the increase in pH that normally occurs in bacterial cultures containing urea. Urease activity was measured colorimetrically by the formation of ammonium ions. The green tea and Uva-Ursi preparations reduced urease activity in a soluble extract of S. saprophyticus by more than 75%. Two herbal mixtures were weakly inhibitory and reduced activity by about 25%, but the other products had little or no effect. The green tea and Uva-Ursi extracts also inhibited urease activity in whole cells by more than 75%. One of the herbal products (WishGarden UTI) showed some inhibition of urease activity but the other (UTI Clear) did not. The green tea and Uva-Ursi preparations prevented the increase in pH that normally occurs when S. saprophyticus is grown in an artificial urine medium, but this was due primarily to bacterial death. The WishGarden UTI preparation could partially delay the pH increase while allowing some cells to remain viable. These results indicate that only a few of the commercially available over-the-counter plant preparations commonly used for the treatment of urinary tract infections (UTIs) can inhibit the urease activity from S. saprophyticus. While over-the-counter plant preparations may be considered an alternative to traditional antibiotics for the treatment of UTIs, they should be used with caution and a product should be matched to the properties of the virulence factors of the bacterial pathogen involved. © 2017 The Society for Applied Microbiology.

A COMPUTATIONAL WORKBENCH ENVIRONMENT FOR VIRTUAL POWER PLANT SIMULATION

International Nuclear Information System (INIS)

Mike Bockelie; Dave Swensen; Martin Denison

2002-01-01

This is the fifth Quarterly Technical Report for DOE Cooperative Agreement No: DE-FC26-00NT41047. The goal of the project is to develop and demonstrate a computational workbench for simulating the performance of Vision 21 Power Plant Systems. Within the last quarter, our efforts have become focused on developing an improved workbench for simulating a gasifier based Vision 21 energyplex. To provide for interoperability of models developed under Vision 21 and other DOE programs, discussions have been held with DOE and other organizations developing plant simulator tools to review the possibility of establishing a common software interface or protocol to use when developing component models. A component model that employs the CCA protocol has successfully been interfaced to our CCA enabled workbench. To investigate the software protocol issue, DOE has selected a gasifier based Vision 21 energyplex configuration for use in testing and evaluating the impacts of different software interface methods. A Memo of Understanding with the Cooperative Research Centre for Coal in Sustainable Development (CCSD) in Australia has been completed that will enable collaborative research efforts on gasification issues. Preliminary results have been obtained for a CFD model of a pilot scale, entrained flow gasifier. A paper was presented at the Vision 21 Program Review Meeting at NETL (Morgantown) that summarized our accomplishments for Year One and plans for Year Two and Year Three

Computer aided process control equipment at the Karlsruhe reprocessing pilot plant, WAK

International Nuclear Information System (INIS)

Winter, R.; Finsterwalder, L.; Gutzeit, G.; Reif, J.; Stollenwerk, A.H.; Weinbrecht, E.; Weishaupt, M.

1991-01-01

A computer aided process control system has been installed at the Karlsruhe Spent Fuel Reprocessing Plant, WAK. All necessary process control data of the first extraction cycle is collected via a data collection system and is displayed in suitable ways on a screen for the operator in charge of the unit. To aid verification of displayed data, various measurements are associated to each other using balance type process modeling. Thus, deviation of flowsheet conditions and malfunctioning of measuring equipment are easily detected. (orig.) [de

Colour and toxic characteristics of metakaolinite-hematite pigment for integrally coloured concrete, prepared from iron oxide recovered from a water treatment plant of an abandoned coal mine

Science.gov (United States)

Sadasivam, Sivachidambaram; Thomas, Hywel Rhys

2016-07-01

A metakaolinite-hematite (KH) red pigment was prepared using an ocherous iron oxide sludge recovered from a water treatment plant of an abandoned coal mine. The KH pigment was prepared by heating the kaolinite and the iron oxide sludge at kaolinite's dehydroxylation temperature. Both the raw sludge and the KH specimen were characterised for their colour properties and toxic characteristics. The KH specimen could serve as a pigment for integrally coloured concrete and offers a potential use for the large volumes of the iron oxide sludge collected from mine water treatment plants.

Hanford Waste Vitrification Plant full-scale feed preparation testing with water and process simulant slurries

International Nuclear Information System (INIS)

Gaskill, J.R.; Larson, D.E.; Abrigo, G.P.

1996-03-01

The Hanford Waste Vitrification Plant was intended to convert selected, pretreated defense high-level waste and transuranic waste from the Hanford Site into a borosilicate glass. A full-scale testing program was conducted with nonradioactive waste simulants to develop information for process and equipment design of the feed-preparation system. The equipment systems tested included the Slurry Receipt and Adjustment Tank, Slurry Mix Evaporator, and Melter-Feed Tank. The areas of data generation included heat transfer (boiling, heating, and cooling), slurry mixing, slurry pumping and transport, slurry sampling, and process chemistry. 13 refs., 129 figs., 68 tabs

Human-machine interaction in nuclear power plants

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu

2005-01-01

Advanced nuclear power plants are generally large complex systems automated by computers. Whenever a rate plant emergency occurs the plant operators must cope with the emergency under severe mental stress without committing any fatal errors. Furthermore, the operators must train to improve and maintain their ability to cope with every conceivable situation, though it is almost impossible to be fully prepared for an infinite variety of situations. In view of the limited capability of operators in emergency situations, there has been a new approach to preventing the human error caused by improper human-machine interaction. The new approach has been triggered by the introduction of advanced information systems that help operators recognize and counteract plant emergencies. In this paper, the adverse effect of automation in human-machine systems is explained. The discussion then focuses on how to configure a joint human-machine system for ideal human-machine interaction. Finally, there is a new proposal on how to organize technologies that recognize the different states of such a joint human-machine system

Availability of fusion plants employing a Monte Carlo simulation computer code

International Nuclear Information System (INIS)

Musicki, Z.

1984-01-01

The fusion facilities being built or designed will have availability problems due to their complexity and employment of not yet fully developed technologies. Low availability of test facilities will have an adverse impact on the learning time and will therefore push back the commercialization date of fusion. Low availability of commercial electric power plants will increase the cost of electricity and make fusion a less-attractive power source. Thus, the time to study the availability problems of fusion plants and suggest improvements is now, before costly mistakes are committed. This study is an initial effort in the area and is an attempt to develop methods for calculation of system's performance, specifically its availability, start collecting necessary data and identify the areas where data are lacking, as well as to point out the subsystems where resources need to be applied in order to bring about an acceptable system performance. The method used to study availability is a simulation computer code based on the Monte Carlo process and developed by the author. The fusion systems analyzed were TASKA (a tandem mirror test facility design) and MARS (a tandem mirror power plant design). The model and available data were employed to find that the most critical subsystems needing further work are the neutral beams, RF heating subsystems, direct convertor, and certain magnets

Lessons learned in streamlining the preparation of SNM standard solutions

International Nuclear Information System (INIS)

Clark, J.P.; Johnson, S.R.

1986-01-01

Improved safeguard measurements have produced a demand for greater quantities of reliable SNM solution standards. At the Savannah River Plant (SRP), the demand for these standards has been met by several innovations to improve the productivity and reliability of standards preparations. With the use of computer controlled balance, large batches of SNM stock solutions are prepared on a gravimetric basis. Accurately dispensed quantities of the stock solution are weighed and stored in bottles. When needed, they are quantitatively transferred to tared containers, matrix adjusted to target concentrations, weighed, and measured for density at 25 0 C. Concentrations of SNM are calculated both gravimetrically and volumetrically. Calculated values are confirmed analytically before the standards are used in measurement control program (MCP) activities. The lessons learned include: MCP goals include error identification and management. Strategy modifications are required to improve error management. Administrative controls can minimize certain types of errors. Automation can eliminate redundancy and streamline preparations. Prudence and simplicity enhance automation success. The effort expended to increase productivity has increased the reliability of standards and provided better documentation for quality assurance

Assessment of three root canal preparation techniques on root canal geometry using micro-computed tomography: In vitro study

Directory of Open Access Journals (Sweden)

Shaikha M Al-Ali

2012-01-01

Full Text Available Aim: To assess the effects of three root canal preparation techniques on canal volume and surface area using three-dimensionally reconstructed root canals in extracted human maxillary molars. Materials and Methods: Thirty extracted Human Maxillary Molars having three separate roots and similar root shape were randomly selected from a pool of extracted teeth for this study and stored in normal saline solution until used. A computed tomography scanner (Philips Brilliance CT 64-slice was used to analyze root canals in extracted maxillary molars. Specimens were scanned before and after canals were prepared using stainless steel K-Files, Ni-Ti rotary ProTaper and rotary SafeSiders instruments. Differences in dentin volume removed, the surface area, the proportion of unchanged area and canal transportation were calculated using specially developed software. Results: Instrumentation of canals increased volume and surface area. Statistical analysis found a statistically significant difference among the 3 groups in total change in volume (P = 0.001 and total change in surface area (P = 0.13. Significant differences were found when testing both groups with group III (SafeSiders. Significant differences in change of volume were noted when grouping was made with respect to canal type (in MB and DB (P < 0.05. Conclusion: The current study used computed tomography, an innovative and non destructive technique, to illustrate changes in canal geometry. Overall, there were few statistically significant differences between the three instrumentation techniques used. SafeSiders stainless steel 40/0.02 instruments exhibit a greater cutting efficiency on dentin than K-Files and ProTaper. CT is a new and valuable tool to study root canal geometry and changes after preparation in great details. Further studies with 3D-techniques are required to fully understand the biomechanical aspects of root canal preparation.

KWU Nuclear Plant Analyzer

International Nuclear Information System (INIS)

Bennewitz, F.; Hummel, R.; Oelmann, K.

1986-01-01

The KWU Nuclear Plant Analyzer is a real time engineering simulator based on the KWU computer programs used in plant transient analysis and licensing. The primary goal is to promote the understanding of the technical and physical processes of a nuclear power plant at an on-site training facility. Thus the KWU Nuclear Plant Analyzer is available with comparable low costs right at the time when technical questions or training needs arise. This has been achieved by (1) application of the transient code NLOOP; (2) unrestricted operator interaction including all simulator functions; (3) using the mainframe computer Control Data Cyber 176 in the KWU computing center; (4) four color graphic displays controlled by a dedicated graphic computer, no control room equipment; and (5) coupling of computers by telecommunication via telephone

IAEA expert assessment of basic issues associated with the preparation and implementation of the Temelin nuclear power plant

International Nuclear Information System (INIS)

Horak, B.

1990-01-01

An independent IAEA team composed of foreign experts was invited to Temelin with the aim to review the plant with respect to nuclear safety of the site, organization of construction activities, implementation of the construction including quality assurance aspects, preparation of operation, radioactive waste management, reactor core physics, and safety system design. Final reports conclude that the site has a low seismicity and favorable meteorological, hydrogeological and demographic conditions, and thus is well suited to the construction of a nuclear power plant. It has been suggested that within CEZ (the Czech Power Company, the utility operating all power plants in the Czech Republic), all activities associated with nuclear power should be concentrated in one division which would be responsible for safety supervision, technical assistance, and overall construction management. Particular efforts must be devoted to quality assurance. The expert team stated that in its design, the WWER-1000 reactor approaches state-of-the-art pressurized water reactors which are being launched in other countries. (M.D.)

Preliminary Computational Analysis of the (HIRENASD) Configuration in Preparation for the Aeroelastic Prediction Workshop

Science.gov (United States)

Chwalowski, Pawel; Florance, Jennifer P.; Heeg, Jennifer; Wieseman, Carol D.; Perry, Boyd P.

2011-01-01

This paper presents preliminary computational aeroelastic analysis results generated in preparation for the first Aeroelastic Prediction Workshop (AePW). These results were produced using FUN3D software developed at NASA Langley and are compared against the experimental data generated during the HIgh REynolds Number Aero- Structural Dynamics (HIRENASD) Project. The HIRENASD wind-tunnel model was tested in the European Transonic Windtunnel in 2006 by Aachen University0s Department of Mechanics with funding from the German Research Foundation. The computational effort discussed here was performed (1) to obtain a preliminary assessment of the ability of the FUN3D code to accurately compute physical quantities experimentally measured on the HIRENASD model and (2) to translate the lessons learned from the FUN3D analysis of HIRENASD into a set of initial guidelines for the first AePW, which includes test cases for the HIRENASD model and its experimental data set. This paper compares the computational and experimental results obtained at Mach 0.8 for a Reynolds number of 7 million based on chord, corresponding to the HIRENASD test conditions No. 132 and No. 159. Aerodynamic loads and static aeroelastic displacements are compared at two levels of the grid resolution. Harmonic perturbation numerical results are compared with the experimental data using the magnitude and phase relationship between pressure coefficients and displacement. A dynamic aeroelastic numerical calculation is presented at one wind-tunnel condition in the form of the time history of the generalized displacements. Additional FUN3D validation results are also presented for the AGARD 445.6 wing data set. This wing was tested in the Transonic Dynamics Tunnel and is commonly used in the preliminary benchmarking of computational aeroelastic software.

Computer code structure for evaluation of fire protection measures and fighting capability at nuclear plants

International Nuclear Information System (INIS)

Anton, V.

1997-01-01

In this work a computer code structure for Fire Protection Measures (FPM) and Fire Fighting Capability (FFC) at Nuclear Power Plants (NPP) is presented. It allows to evaluate the category (satisfactory (s), needs for further evaluation (n), unsatisfactory (u)) to which belongs the given NPP for a self-control in view of an IAEA inspection. This possibility of a self assessment resulted from IAEA documents. Our approach is based on international experience gained in this field and stated in IAEA recommendations. As an illustration we used the FORTRAN programming language statement to make clear the structure of the computer code for the problem taken into account. This computer programme can be conceived so that some literal message in English and Romanian languages be displayed beside the percentage assessments. (author)

COMPUTING

CERN Multimedia

P. McBride

It has been a very active year for the computing project with strong contributions from members of the global community. The project has focused on site preparation and Monte Carlo production. The operations group has begun processing data from P5 as part of the global data commissioning. Improvements in transfer rates and site availability have been seen as computing sites across the globe prepare for large scale production and analysis as part of CSA07. Preparations for the upcoming Computing Software and Analysis Challenge CSA07 are progressing. Ian Fisk and Neil Geddes have been appointed as coordinators for the challenge. CSA07 will include production tests of the Tier-0 production system, reprocessing at the Tier-1 sites and Monte Carlo production at the Tier-2 sites. At the same time there will be a large analysis exercise at the Tier-2 centres. Pre-production simulation of the Monte Carlo events for the challenge is beginning. Scale tests of the Tier-0 will begin in mid-July and the challenge it...

A computational model for evaluating the effects of attention, memory, and mental models on situation assessment of nuclear power plant operators

International Nuclear Information System (INIS)

Lee, Hyun-Chul; Seong, Poong-Hyun

2009-01-01

Operators in nuclear power plants have to acquire information from human system interfaces (HSIs) and the environment in order to create, update, and confirm their understanding of a plant state, as failures of situation assessment may cause wrong decisions for process control and finally errors of commission in nuclear power plants. A few computational models that can be used to predict and quantify the situation awareness of operators have been suggested. However, these models do not sufficiently consider human characteristics for nuclear power plant operators. In this paper, we propose a computational model for situation assessment of nuclear power plant operators using a Bayesian network. This model incorporates human factors significantly affecting operators' situation assessment, such as attention, working memory decay, and mental model. As this proposed model provides quantitative results of situation assessment and diagnostic performance, we expect that this model can be used in the design and evaluation of human system interfaces as well as the prediction of situation awareness errors in the human reliability analysis.

A computational model for evaluating the effects of attention, memory, and mental models on situation assessment of nuclear power plant operators

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyun-Chul [Instrumentation and Control/Human Factors Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)], E-mail: leehc@kaeri.re.kr; Seong, Poong-Hyun [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

2009-11-15

Operators in nuclear power plants have to acquire information from human system interfaces (HSIs) and the environment in order to create, update, and confirm their understanding of a plant state, as failures of situation assessment may cause wrong decisions for process control and finally errors of commission in nuclear power plants. A few computational models that can be used to predict and quantify the situation awareness of operators have been suggested. However, these models do not sufficiently consider human characteristics for nuclear power plant operators. In this paper, we propose a computational model for situation assessment of nuclear power plant operators using a Bayesian network. This model incorporates human factors significantly affecting operators' situation assessment, such as attention, working memory decay, and mental model. As this proposed model provides quantitative results of situation assessment and diagnostic performance, we expect that this model can be used in the design and evaluation of human system interfaces as well as the prediction of situation awareness errors in the human reliability analysis.

Conditions of development of professional competence by preparation of the teacher in the field of a technique of training to computer science

Directory of Open Access Journals (Sweden)

Ольга Юрьевна Заславская

2009-12-01

Full Text Available In article results of research of formation of professional competence of teachers of computer science in modern conditions of modernization of an education system are described. In the conditions of formation information, it is necessary to carry out preparation of the teacher possessing administrative competence, necessary quality first of all in the course of training of the theory and a technique of training to computer science.

Effects of site preparation treatments on early growth and survival of planted longleaf pine (Pinus palustris Mill.) seedlings in North Carolina

Science.gov (United States)

Benjamin O. Knapp; G. Geoff Wang; Joan L. Walker; Susan Cohen

2006-01-01

We tested the effects of eight site preparation treatments on early growth and survival of container-grown longleaf pine (Pinus palustris Mill.) seedlings. Treatments included an untreated check, six combinations of two initial vegetation control treatments (chopping or herbicide) with three planting site conditions (flat [no additional treatment],...

Modernization of the plant computer C. N. Cofrentes; Modernizacion del computador de planta de C. N. Cofrentes

Energy Technology Data Exchange (ETDEWEB)

Sanchez, M.; Zuriaga, J. V.

2011-07-01

Cofrentes NPP C and I systems modernization plan identifies a number of systems which upgrade is a priority mainly because of obsolescence criteria and the need for technological improvement. In 2009, the Turbine and Bypass Control Systems modernization project concluded successfully, paving the way for updating the big brother of Cofrentes NPP, the Plant Process Computer, which is connected to all process systems to collect data, store, analyze and present them to the end user in any plant operational mode. (Author)

The purpose and organisation of reliability and risk assessment studies for power plant in operation

International Nuclear Information System (INIS)

Ohlmeier, H.

1989-01-01

Upon recommendation of the Reaktorsicherheitskommission RSK, specific, probabilistic safety analyses have to be made within the next few years for every nuclear power plant in operation. The paper deals with the activities and tasks and the necessary organisational preparations to be made for carrying out the studies. A systematic determination of reliability parameters and establishment of suitable computer codes are one of the major tasks in the preparatory phase, and information for further quantification of safety reserves and more plant-specific emergency management plans will be major results of the studies. (orig.) [de

Application of meteorology to safety at nuclear plants

International Nuclear Information System (INIS)

1968-01-01

This report was prepared on behalf of the International Atomic Energy Agency by an international panel of experts who met at the Agency's headquarters from 10 to 14 April 1967. The application of meteorology to safety at nuclear plants is discussed in connection with site selection, design and construction, operation, and emergency planning and action. The final chapter considers the training to be given to operators and health and safety personnel on meteorology problems. The appendix gives a simple method for computing air concentration values at ground level. An extensive bibliography is also included.

Laser-optical methods and systems of computer-automated investigation of bio-objects (plants, seeds, food products, and others)

Science.gov (United States)

Lisker, Joseph S.

1999-01-01

A new conception of the scientific problem of information exchange in the system plant-man-environment is developed. The laser-optical methods and the system are described which allow computer automated investigation of bio-objects without damaging their vital function. The results of investigation of optical-physiological features of plants and seeds are presented. The effects of chlorophyll well and IR beg are discovered for plants and also the effects os water pumping and protein transformations are shown for seeds. The perspectives of the use of the optical methods and equipment suggested to solve scientific problems of agriculture are discussed.

THE EFFECT OF PRESSURE SPRAYING PLANTS WITH MICROBIOLOGICAL PREPARATIONS TO MAINTAIN THE VIABILITY OF MICROORGANISMS AND THEIR AMOUNT

OpenAIRE

Kotlyarov V. V.; Sedinina N. V.; Donchenko D. Y.; Kotlyarov D. V.

2016-01-01

Questions of microbial plant protection become more relevant. The use of microorganisms can solve the following problems: biologization of agriculture and sanitation of soil. Application of various physical factors affecting the microorganisms reduces their number. This influences the efficiency of their use. This article gives examples of the application of pressure in the biotechnological process of microbial preparations and their use in the process of spraying. The effect of pressure on n...

Application of artificial intelligence in coal preparation

Energy Technology Data Exchange (ETDEWEB)

Kuang, Y.; Deng, J.; Liu, H. [China University of Mining and Technology, Xuzhou (China). School of Chemical Engineering and Technology

2001-11-01

The general situation of using AI (Artificial intelligence) technology in coal preparation was introduced. The expert systems of coal preparation plant design, the expert management system of coal preparation plant, and the intelligent data-drawing bank were discussed. Some opinions about their foundation and method of knowledge expressing, inference, knowledge discovery of databases were presented. It is pointed out that an industrial system such as coal preparation is big and complex, so it is necessary and also difficult to use AI technology in these systems. Because the types of knowledge are different, there are various knowledge expressions and model of knowledge inference, hence only comprehensive methods suitable for the characters of the system may be used. 14 refs., 5 figs.

NET IBK Computer code package for the needs of planning, construction and operation of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Matausek, M V; Kocic, A; Marinkovic, N; Milosevic, M; Stancic, V [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

1978-07-01

Within the Nuclear Engineering Laboratory of the Boris Kidric Institute of Nuclear Sciences (NET IBK) a systematic work has been performed on collecting nuclear data for reactor calculation needs, on developing own methods and computing programs for reactor calculations, as well as on adapting and applying the foreign methods and codes. In this way a complete library of computer programs was formed for precise prediction of nuclear fuel burnup and depletion, for evaluation of the Power distribution variations with irradiation, for computing the amount of produced plutonium and its number densities etc. Programs for evaluation of location of different types of safety and economic analysis have been developed as well. The aim of this paper is to present our abilities to perform complex computations needed for planning, constructing and operating the nuclear power plants, by describing the NET IBK computer programs package. (author)

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.

Effect of humic-plant feed preparations on biochemical blood parameters of laying hens in deep litter housing system.

Science.gov (United States)

Bubel, F; Dobrzański, Z; Gaweł, A; Pogoda-Sewerniak, K; Grela, E R

2015-01-01

An influence of various humic-plant feed additives based on some herbs (nettle, chamomile, yarrow, perforatum), lucerne and humic materials on biochemical indices of Lohmann Brown (LB) layers blood plasma was estimated. Hens were housed in deep litter system, 20 birds in a group. Four groups were formed: control (C - standard feeding), and experimental, supplemented with prepara- tions: E-1 herbal-humic, E-2 humic-herbal and E-3--humic-lucerne. Hens were placed in the pens on the 16th week of life, addition of preparations with standard food mixture started at the 22nd wk and lasted until 66th wk of life. Blood for analyses was collected four times in the following periods: 27, 37, 54 and 65th wk of life. The applied humic-plant preparations to a limited degree affected the values of examined biochemical parameters in serum: total protein (TP), albumins (Albs), glucose (Glu), urea, triacylglycerols (TAG), total cholesterol (TCh), alanine aminotransferase (ALT), aspartate aminot- ransferase (AST) and alkaline phosphatase (ALP). It is difficult to determine based on these study, which preparation is one the most active biologically, however is seems that humic-lucerne prepara- tion affected the examined blood parameters to the highest degree. The reference values ranges in hens blood serum LB hens were proposed for: TP (43-65 g/l), Albs (15-22 g/l), urea (0.5-1.2 mmol/l), Glu 10-15 mmol/l), TCh (2.2-4.5 mmol/l), TAG (10-24 mmol/l), AST (4-12 U/l), ALT (150-280 mmol/l) and ALP (190-350 U/l).

Intelligent and interactive computer image of a nuclear power plant: The ImagIn project

International Nuclear Information System (INIS)

Haubensack, D.; Malvache, P.; Valleix, P.

1998-01-01

The ImagIn project consists in a method and a set of computer tools apt to bring perceptible and assessable improvements in the operational safety of a nuclear plant. Its aim is to design an information system that would maintain a highly detailed computerized representation of a nuclear plant in its initial state and throughout its in-service life. It is not a tool to drive or help driving the nuclear plant, but a tool that manages concurrent operations that modify the plant configuration in a very general was (maintenance for example). The configuration of the plant, as well as rules and constraints about it, are described in a object-oriented knowledge database, which is built using a generic ImagIn meta-model based on the semantical network theory. An inference engine works on this database and is connected to reality through interfaces to operators and captors on the installation; it verifies constantly in real-time the consistency of the database according to its inner rules, and reports eventual problems to concerned operators. A special effort is made on interfaces to provide natural and intuitive tools (using virtual reality, natural language, voice recognition and synthesis). A laboratory application on a fictive but realistic installation already exists and is used to simulate various tests and scenarii. A real application is being constructed on Siloe, an experimental reactor of the CEA. (author)

COMPUTING

CERN Multimedia

P. McBride

The Computing Project is preparing for a busy year where the primary emphasis of the project moves towards steady operations. Following the very successful completion of Computing Software and Analysis challenge, CSA06, last fall, we have reorganized and established four groups in computing area: Commissioning, User Support, Facility/Infrastructure Operations and Data Operations. These groups work closely together with groups from the Offline Project in planning for data processing and operations. Monte Carlo production has continued since CSA06, with about 30M events produced each month to be used for HLT studies and physics validation. Monte Carlo production will continue throughout the year in the preparation of large samples for physics and detector studies ramping to 50 M events/month for CSA07. Commissioning of the full CMS computing system is a major goal for 2007. Site monitoring is an important commissioning component and work is ongoing to devise CMS specific tests to be included in Service Availa...

Evaluation methods for corrosion damage of components in cooling systems of nuclear power plants by coupling analysis of corrosion and flow dynamics (1). Major targets and development strategies of the evaluation methods

International Nuclear Information System (INIS)

Naitoh, Masanori; Uchida, Shunsuke; Koshizuka, Seiichi; Ninokata, Hisashi; Hiranuma, Naoki; Dosaki, Koji; Nishida, Koji; Akiyama, Minoru; Saitoh, Hiroaki

2008-01-01

Problems in major components and structural materials in nuclear power plants have often been caused by flow induced vibration and corrosion and their overlapping effects. In order to establish safe and reliable plant operation, future problems for structural materials should be predicted based on combined analyses of flow dynamics and corrosion and they should be mitigated before becoming serious issues for plant operation. Three approaches have been prepared for predicting future problems in structural materials: 1. Computer program packages for predicting future corrosion fatigue on structural materials, 2. Computer program packages for predicting future corrosion damage on structural materials, and 3. Computer program packages for predicting wall thinning caused by flow accelerated corrosion. General features of evaluation methods and their computer packages, technical innovations required for their development, and application plans for the developed approaches for plant operation are introduced in this paper. (author)

Preparation of Low Molecular Weight Chitosan by Radiation and its Application for Plant Growth Promoter. Chapter 10

Energy Technology Data Exchange (ETDEWEB)

Darwis, D.; Puspitasari, T.; Iramani, D.; Susilowati, Sri; Pangerteni, D.S., E-mail: darmawan_p3tir@batan.go.id [National Nuclear Energy Agency, Centre for Application of Isotopes and Radiation Technology (Indonesia)

2014-07-15

Chitosan was prepared through the alkaline deacetylation of chitin from shrimp shell waste. Chitosan with a degree of deacetylation of about 70% was produced by hot alkaline deacetylation (DDA) at 90°C for 8 hours or at room temperature deacetylation for 7 days. Through these processes, chitosan with an average molecular weight (Mw) of 141 k Dalton was obtained. Low molecular weight chitosan, Mw 14 k Dalton called “Fitosan” was prepared by irradiating chitosan using gamma rays at a dose of 75 kGy. The results showed that gamma irradiation is an effective method of degrading chitosan by cleavages of glycosidic bond. To improve crop yields and suppress diseases due to virus, bacteria, and fungi, Fitosan was successfully applied to chili, potato, and soybean. Socio-economic impacts of the use of Fitosan on the plants include increased income and improvement of the welfare of farmers. (author)

CFD analyses of steam and hydrogen distribution in a nuclear power plant

International Nuclear Information System (INIS)

Siccama, N.B.; Houkema, M.; Komen, E.M.J.

2003-01-01

A detailed three-dimensional Computational Fluid Dynamics (CFD) model of the containment of the nuclear power plant has been prepared in order to assess possible multidimensional phenomena. In a first code-to-code comparison step, the CFD model has been used to compute a reference accident scenario which has been analysed earlier with the lumped parameter code SPECTRA. The CFD results compare qualitatively well with the SPECTRA results. Subsequently, the actual steam jet from the primary system has been modelled in the CFD code in order to determine the hydrogen distribution for this realistically modelled source term. Based on the computed hydrogen distributions, it has been determined when use of lumped parameter codes is allowed and when use of CFD codes is required. (author)

Long term operation of nuclear power plants in Spain: preparing for the future

Energy Technology Data Exchange (ETDEWEB)

Marcelles, I.; Frutos, E.; Jardi, X.; Cosgaya, F., E-mail: imarcelles@tecnatom.es [Tecnatom, S. A., Av. Montes de Oca 1, 28703 San Sebastian de los Reyes, Madrid (Spain)

2017-09-15

The Spanish nuclear industry is preparing for the Long Term Operation (LTO) of its complete fleet. Therefore, an important number of activities are being currently developed in order to achieve the safe and economical life extension of the operational life of the Spanish nuclear power plants. This paper describes the main activities that will be performed to meet the licensing requirements, in order to be granted and operating license for LTO, such as the development of Ageing Management Plans (Amp), Time Limited Ageing Analysis (TLAA) as well as databases and software tools to support LTO. In addition to this, this paper will describe the implementation of the NDE activities included in the AMPs and some of the research and development programs that the Spanish nuclear industry research is working on related to LTO (e.g. cable ageing, concrete degradation, etc.) (Author)

Long term operation of nuclear power plants in Spain: preparing for the future

International Nuclear Information System (INIS)

Marcelles, I.; Frutos, E.; Jardi, X.; Cosgaya, F.

2017-09-01

The Spanish nuclear industry is preparing for the Long Term Operation (LTO) of its complete fleet. Therefore, an important number of activities are being currently developed in order to achieve the safe and economical life extension of the operational life of the Spanish nuclear power plants. This paper describes the main activities that will be performed to meet the licensing requirements, in order to be granted and operating license for LTO, such as the development of Ageing Management Plans (Amp), Time Limited Ageing Analysis (TLAA) as well as databases and software tools to support LTO. In addition to this, this paper will describe the implementation of the NDE activities included in the AMPs and some of the research and development programs that the Spanish nuclear industry research is working on related to LTO (e.g. cable ageing, concrete degradation, etc.) (Author)

High performance simulation for the Silva project using the tera computer

International Nuclear Information System (INIS)

Bergeaud, V.; La Hargue, J.P.; Mougery, F.; Boulet, M.; Scheurer, B.; Le Fur, J.F.; Comte, M.; Benisti, D.; Lamare, J. de; Petit, A.

2003-01-01

In the context of the SILVA Project (Atomic Vapor Laser Isotope Separation), numerical simulation of the plant scale propagation of laser beams through uranium vapour was a great challenge. The PRODIGE code has been developed to achieve this goal. Here we focus on the task of achieving high performance simulation on the TERA computer. We describe the main issues for optimizing the parallelization of the PRODIGE code on TERA. Thus, we discuss advantages and drawbacks of the implemented diagonal parallelization scheme. As a consequence, it has been found fruitful to fit out the code in three aspects: memory allocation, MPI communications and interconnection network bandwidth usage. We stress out the interest of MPI/IO in this context and the benefit obtained for production computations on TERA. Finally, we shall illustrate our developments. We indicate some performance measurements reflecting the good parallelization properties of PRODIGE on the TERA computer. The code is currently used for demonstrating the feasibility of the laser propagation at a plant enrichment level and for preparing the 2003 Menphis experiment. We conclude by emphasizing the contribution of high performance TERA simulation to the project. (authors)

High performance simulation for the Silva project using the tera computer

Energy Technology Data Exchange (ETDEWEB)

Bergeaud, V.; La Hargue, J.P.; Mougery, F. [CS Communication and Systemes, 92 - Clamart (France); Boulet, M.; Scheurer, B. [CEA Bruyeres-le-Chatel, 91 - Bruyeres-le-Chatel (France); Le Fur, J.F.; Comte, M.; Benisti, D.; Lamare, J. de; Petit, A. [CEA Saclay, 91 - Gif sur Yvette (France)

2003-07-01

In the context of the SILVA Project (Atomic Vapor Laser Isotope Separation), numerical simulation of the plant scale propagation of laser beams through uranium vapour was a great challenge. The PRODIGE code has been developed to achieve this goal. Here we focus on the task of achieving high performance simulation on the TERA computer. We describe the main issues for optimizing the parallelization of the PRODIGE code on TERA. Thus, we discuss advantages and drawbacks of the implemented diagonal parallelization scheme. As a consequence, it has been found fruitful to fit out the code in three aspects: memory allocation, MPI communications and interconnection network bandwidth usage. We stress out the interest of MPI/IO in this context and the benefit obtained for production computations on TERA. Finally, we shall illustrate our developments. We indicate some performance measurements reflecting the good parallelization properties of PRODIGE on the TERA computer. The code is currently used for demonstrating the feasibility of the laser propagation at a plant enrichment level and for preparing the 2003 Menphis experiment. We conclude by emphasizing the contribution of high performance TERA simulation to the project. (authors)

BNFL's application of computer aided engineering to 'THORP' thermal oxide reprocessing plant

International Nuclear Information System (INIS)

Hall-Wilton, M.J.

1990-01-01

BNFL are currently constructing facilities at Sellafield, Cumbria to reprocess thermal oxide fuel for U.K., European and Japanese utilities. Faced with a 3.5bn pound capital program to provide new facilities at Sellafield, BNFL took the opportunity to embrace the new computer aided engineering technologies then emerging in 1981. To give some idea of the commitment made by BNFL to the above many millions of pounds has been invested in hardware, and more on software and people. The 'THORP' (Head End and Chemical Separation Plant) project represents 1.5bn pounds. The introduction of computer aided engineering has provided a clash free design with full assurance that all materials and components used are compatible. Planning in the design offices in conjunction with an experienced construction management team enables the sequence of piping installation to be determined long before the construction teams enter the work area. This planning aspect has been significantly improved by using EVS (Enhanced Visualisation System). The use of supercomputing graphics facilities is stimulating demands from areas of engineering who have previously not sought to use magnetic data from a variety of sources. The result is mainly due to the data being easily accessible to users who have very little computing experience. (N.K.)

Preliminary regulatory assessment of nuclear power plants vulnerabilities

International Nuclear Information System (INIS)

Kostadinov, V.; Petelin, S.

2004-01-01

Preliminary attempts to develop models for nuclear regulatory vulnerability assessment of nuclear power plants are presented. Development of the philosophy and computer tools could be new and important insight for management of nuclear operators and nuclear regulatory bodies who face difficult questions about how to assess the vulnerability of nuclear power plants and other nuclear facilities to external and internal threats. In the situation where different and hidden threat sources are dispersed throughout the world, the assessment of security and safe operation of nuclear power plants is very important. Capability to evaluate plant vulnerability to different kinds of threats, like human and natural occurrences and terrorist attacks and preparation of emergency response plans and estimation of costs are of vital importance for assurance of national security. On the basis of such vital insights, nuclear operators and nuclear regulatory bodies could plan and optimise changes in oversight procedures, organisations, equipment, hardware and software to reduce risks taking into account security and safety of nuclear power plants operation, budget, manpower, and other limitations. Initial qualitative estimations of adapted assessments for nuclear applications are shortly presented. (author)

Standard format and content for the physical protection section of a license application (for facilities other than nuclear power plants)

International Nuclear Information System (INIS)

1976-06-01

The document presented has been prepared as an aid to uniformity and completeness in the preparation and review of the physical protection section of license applications. It is applicable to fuel reprocessing plants, fuel manufacturing plants, SNM tranportation, or other special nuclear material operations involving the possession and use of uranium 235 (contained in uranium enriched to 20 percent or more in the U-235 isotope), uranium 233, or plutonium alone or in any combination in a quantity of 5000 grams or more computed by the formula: grams = (grams contained U-235) + 2.5 (grams U-233 + grams plutonium). The document is not intended to be used for nuclear power plants. The information specified is the minimum needed for a license application. Additional information may be required for completion of the staff review of a particular application

Application of Blind Quantum Computation to Two-Party Quantum Computation

Science.gov (United States)

Sun, Zhiyuan; Li, Qin; Yu, Fang; Chan, Wai Hong

2018-03-01

Blind quantum computation (BQC) allows a client who has only limited quantum power to achieve quantum computation with the help of a remote quantum server and still keep the client's input, output, and algorithm private. Recently, Kashefi and Wallden extended BQC to achieve two-party quantum computation which allows two parties Alice and Bob to perform a joint unitary transform upon their inputs. However, in their protocol Alice has to prepare rotated single qubits and perform Pauli operations, and Bob needs to have a powerful quantum computer. In this work, we also utilize the idea of BQC to put forward an improved two-party quantum computation protocol in which the operations of both Alice and Bob are simplified since Alice only needs to apply Pauli operations and Bob is just required to prepare and encrypt his input qubits.

Application of Blind Quantum Computation to Two-Party Quantum Computation

Science.gov (United States)

Sun, Zhiyuan; Li, Qin; Yu, Fang; Chan, Wai Hong

2018-06-01

Blind quantum computation (BQC) allows a client who has only limited quantum power to achieve quantum computation with the help of a remote quantum server and still keep the client's input, output, and algorithm private. Recently, Kashefi and Wallden extended BQC to achieve two-party quantum computation which allows two parties Alice and Bob to perform a joint unitary transform upon their inputs. However, in their protocol Alice has to prepare rotated single qubits and perform Pauli operations, and Bob needs to have a powerful quantum computer. In this work, we also utilize the idea of BQC to put forward an improved two-party quantum computation protocol in which the operations of both Alice and Bob are simplified since Alice only needs to apply Pauli operations and Bob is just required to prepare and encrypt his input qubits.

Guideline for the procedure of preparing and executing of maintenance and modifications in nuclear power plants (dated May 10th, 1978)

International Nuclear Information System (INIS)

1978-01-01

Based on the terms defined for this guideline and on legal provisions, it is the purpose of this guideline to render a contribution to the guaranteeing of safe operation and to foster the safety of work while taking the safety of the plant into account by means of a uniform procedure for the preparation and execution of maintenance and modifications carried out in nuclear power plants. The criteria to be taken into account and the procedural steps necessary, organisational measures and controls, technical aspects to be taken into account and determinations to be made are given. Matters concerning plant safety (protection of objects) are pointed out, if they are to be taken into account as marginal conditions when determining measures for the safety of work and the safety of the plant. The guideline serves as a basis for the set-up and assessment of a maintenance-regulation adapted to the resp. organisation of the plant and for the elaboration and check-up of the detailed complementary documents as e.g. accident report blanks, cut-off blanks and safety certificates. (orig.) [de

Preparation of computer codes for analyzing sensitivity coefficients of burnup characteristics (2) (Contract research, translated document)

International Nuclear Information System (INIS)

Hanaki, Hiroshi; Sanda, Toshio; Ohashi, Masahisa

2008-10-01

To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library has been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only nuclear characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore, it is thought to improve the prediction accuracy for burnup characteristics using many burnup data of 'Joyo' effectively. It is thought the best way to adjust cross sections using sensitivity coefficients of burnup characteristics to utilize burnup data of 'Joyo'. It is able to know the accuracy quantitatively for burnup characteristics of large LMFBR by analyzing the sensitivity coefficients. Therefore in this work computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared since 1992. In 1992 cross-section adjustment was done by using the data of 'Joyo' and the effect was studied. In this year the adequacy of the codes was studied with a view of applying of design of large LMFBR cores. The results are as follows: (1) The computer codes which could analyze sensitivity coefficients of burnup characteristics taking into consideration plural cycles and refueling were prepared, therefore it came of be able to adjust cross sections using burnup data and to estimate the accuracy for design of large LMFBR cores. The characteristics are not only burnup reactivity loss, breeding ratio but also number density, criticality, reactivity worth, reaction rate ratio, and reaction rate

[COMPUTER ASSISTED DESIGN AND ELECTRON BEAMMELTING RAPID PROTOTYPING METAL THREE-DIMENSIONAL PRINTING TECHNOLOGY FOR PREPARATION OF INDIVIDUALIZED FEMORAL PROSTHESIS].

Science.gov (United States)

Liu, Hongwei; Weng, Yiping; Zhang, Yunkun; Xu, Nanwei; Tong, Jing; Wang, Caimei

2015-09-01

To study the feasibility of preparation of the individualized femoral prosthesis through computer assisted design and electron beammelting rapid prototyping (EBM-RP) metal three-dimensional (3D) printing technology. One adult male left femur specimen was used for scanning with 64-slice spiral CT; tomographic image data were imported into Mimics15.0 software to reconstruct femoral 3D model, then the 3D model of individualized femoral prosthesis was designed through UG8.0 software. Finally the 3D model data were imported into EBM-RP metal 3D printer to print the individualized sleeve. According to the 3D model of individualized prosthesis, customized sleeve was successfully prepared through the EBM-RP metal 3D printing technology, assembled with the standard handle component of SR modular femoral prosthesis to make the individualized femoral prosthesis. Customized femoral prosthesis accurately matching with metaphyseal cavity can be designed through the thin slice CT scanning and computer assisted design technology. Titanium alloy personalized prosthesis with complex 3D shape, pore surface, and good matching with metaphyseal cavity can be manufactured by the technology of EBM-RP metal 3D printing, and the technology has convenient, rapid, and accurate advantages.

Computational investigation of small RNAs in the establishment of root nodules and arbuscular mycorrhiza in leguminous plants.

Science.gov (United States)

Jin, Danfeng; Meng, Xianwen; Wang, Yue; Wang, Jingjing; Zhao, Yuhua; Chen, Ming

2018-01-03

Many small RNAs have been confirmed to play important roles in the development of root nodules and arbuscular mycorrhiza. In this study, we carried out the identification of certain small RNAs in leguminous plants (Medicago truncatula, soybean, peanut and common bean), such as miRNAs, tRFs and srRNAs, as well as the computational investigation of their regulations. Thirty miRNAs were predicted to be involved in establishing root nodules and mycorrhiza, and 12 of them were novel in common bean and peanut. The generation of tRFs in M. truncatula was not associated with tRNA gene frequencies and codon usage. Six tRFs exhibited different expressions in mycorrhiza and root nodules. Moreover, srRNA 5.8S in M. truncatula was generated from the regions with relatively low conservation at the rRNA 3' terminal. The protein-protein interactions between the proteins encoded by the target genes of miRNAs, tRFs and srRNAs were computed. The regulation of these three types of sRNAs in the symbiosis between leguminous plants and microorganisms is not a single regulation of certain signaling or metabolic pathways but a global regulation for the plants to own growth or specific events in symbiosis.

POPCYCLE: a computer code for calculating nuclear and fossil plant levelized life-cycle power costs

International Nuclear Information System (INIS)

Hardie, R.W.

1982-02-01

POPCYCLE, a computer code designed to calculate levelized life-cycle power costs for nuclear and fossil electrical generating plants is described. Included are (1) derivations of the equations and a discussion of the methodology used by POPCYCLE, (2) a description of the input required by the code, (3) a listing of the input for a sample case, and (4) the output for a sample case

Analyses of transient plant response under emergency situations. 2

International Nuclear Information System (INIS)

Koyama, Kazuya; Hishida, Masahiko

2000-03-01

In order to support development of the dynamic reliability analysis program DYANA, analyses were made on the event sequences anticipated under emergency situations using the plant dynamics simulation computer code Super-COPD. In this work 9 sequences were analyzed and integrated into an input file for preparing the functions for DYANA using the analytical model and input data which developed for Super-COPD in the previous work. These sequences could not analyze in the previous work, which were categorized into the PLOHS (Protected Loss of Heat Sink) event. (author)

Nuclear power plant control and instrumentation 1982. Proceedings of an international symposium on nuclear power plant control and instrumentation

International Nuclear Information System (INIS)

1983-01-01

Ever increasing demands for nuclear power plant safety and availability imply a need for the introduction of modern measurement and control methods, together with data processing techniques based on the latest advances in electronic components, transducers and computers. Nuclear power plant control and instrumentation is therefore an extremely rapidly developing field. The present symposium, held in Munich, FR Germany, was prepared with the help of the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation and organized in close co-operation with the Gesellschaft fur Reaktorsicherheit, Federal Republic of Germany. A number of developments were highlighted at the Munich symposium: - The increased use of computers can bring clear advantages and this technique is now proven as a tool for supervising and controlling plant operation. Advanced computerized systems for operator support are being developed on a large scale in many countries. The progress in this field is quite obvious, especially in disturbance analysis, safety parameter display, plant operator guidance and plant diagnostics. The new trend of introducing computers and microprocessors in protection systems makes it easy to implement 'defence-in-depth' strategies which give better assurance of correct system responses and also prevent unnecessary reactor trips, thus improving plant availability. The introduction of computerized systems for control of reactor power, reactor water level and reactor pressure as well as for reactor start-up and shut-down could improve the reliability and availability of nuclear power plants. The rapid technical development in the area of control and instrumentation makes it necessary to plan for at least one replacement of obsolete equipment in the course of the 30 years lifetime of a nuclear power plant and retrofitting of currently operating reactors with new control systems. Major design improvements and regulatory requirements also require

An advanced computational algorithm for systems analysis of tokamak power plants

International Nuclear Information System (INIS)

Dragojlovic, Zoran; Rene Raffray, A.; Najmabadi, Farrokh; Kessel, Charles; Waganer, Lester; El-Guebaly, Laila; Bromberg, Leslie

2010-01-01

A new computational algorithm for tokamak power plant system analysis is being developed for the ARIES project. The objective of this algorithm is to explore the most influential parameters in the physical, technological and economic trade space related to the developmental transition from experimental facilities to viable commercial power plants. This endeavor is being pursued as a new approach to tokamak systems studies, which examines an expansive, multi-dimensional trade space as opposed to traditional sensitivity analyses about a baseline design point. The new ARIES systems code consists of adaptable modules which are built from a custom-made software toolbox using object-oriented programming. The physics module captures the current tokamak physics knowledge database including modeling of the most-current proposed burning plasma experiment design (FIRE). The engineering model accurately reflects the intent and design detail of the power core elements including accurate and adjustable 3D tokamak geometry and complete modeling of all the power core and ancillary systems. Existing physics and engineering models reflect both near-term as well as advanced technology solutions that have higher performance potential. To fully assess the impact of the range of physics and engineering implementations, the plant cost accounts have been revised to reflect a more functional cost structure, supported by an updated set of costing algorithms for the direct, indirect, and financial cost accounts. All of these features have been validated against the existing ARIES-AT baseline case. The present results demonstrate visualization techniques that provide an insight into trade space assessment of attractive steady-state tokamaks for commercial use.

Preparative separation of flavonoids from the medicinal plant Davilla elliptica St. Hill. by high-speed counter-current chromatography

OpenAIRE

Rinaldo Daniel; Silva Marcelo Aparecido; Rodrigues Clenilson Martins; Calvo Tamara Regina; Sannomiya Miriam; Santos Lourdes Campaner dos; Vilegas Wagner; Kushima Hélio; Hiruma-Lima Clélia Akiko; Brito Alba Regina Monteiro de Souza

2006-01-01

High-speed counter-current chromatography (HSCCC) is a major tool for the fast separation of natural products from plants. It was used for the preparative isolation of the flavonoid monoglucosides present in the aerial parts of the Davilla elliptica St. Hill. (Dilleniaceae). This species is used in Brazilian folk medicine for the treatment of gastric disorders. The optimum solvent system used was composed of a mixture of ethyl acetate-n-propanol-water (140:8:80, v/v/v) and led to a successful...

Los Alamos Nuclear Plant Analyzer: an interactive power-plant simulation program

International Nuclear Information System (INIS)

Steinke, R.; Booker, C.; Giguere, P.; Liles, D.R.; Mahaffy, J.H.; Turner, M.R.

1984-01-01

The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware-adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

Nuclear Plant Analyzer: an interactive TRAC/RELAP Power-Plant Simulation Program

International Nuclear Information System (INIS)

Steinke, R.; Booker, C.; Giguere, P.; Liles, D.; Mahaffy, J.; Turner, M.; Wiley, R.

1984-01-01

The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

FFTF operations procedures preparation guide. Revision 2

International Nuclear Information System (INIS)

1976-12-01

The Guide is intended to provide guidelines for the initial preparation of FFTF Operating Procedures. The Procedures Preparation Guide was developed from the plan presented and approved in the FFTF Reactor Plant Procedures Plan, PC-1, Revision 3

Present status of NMCC and sample preparation method for bio-samples

International Nuclear Information System (INIS)

Futatsugawa, S.; Hatakeyama, S.; Saitou, S.; Sera, K.

1993-01-01

In NMCC(Nishina Memorial Cyclotron Center) we are doing researches on PET of nuclear medicine (Positron Emission Computed Tomography) and PIXE analysis (Particle Induced X-ray Emission) using a small cyclotron of compactly designed. The NMCC facilities have been opened to researchers of other institutions since April 1993. The present status of NMCC is described. Bio-samples (medical samples, plants, animals and environmental samples) have mainly been analyzed by PIXE in NMCC. Small amounts of bio-samples for PIXE are decomposed quickly and easily in a sealed PTFE (polytetrafluoroethylene) vessel with a microwave oven. This sample preparation method of bio-samples also is described. (author)

High-school students' reasoning while constructing plant growth models in a computer-supported educational environment

Science.gov (United States)

Ergazaki, Marida; Komis, Vassilis; Zogza, Vassiliki

2005-08-01

This paper highlights specific aspects of high-school students’ reasoning while coping with a modeling task of plant growth in a computer-supported educational environment. It is particularly concerned with the modeling levels (‘macro-phenomenological’ and ‘micro-conceptual’ level) activated by peers while exploring plant growth and with their ability to shift between or within these levels. The focus is on the types of reasoning developed in the modeling process, as well as on the reasoning coherence around the central concept of plant growth. The findings of the study show that a significant proportion of the 18 participating dyads perform modeling on both levels, while their ability to shift between them as well as between the various elements of the ‘micro-conceptual’ level is rather constrained. Furthermore, the reasoning types identified in peers’ modeling process are ‘convergent’, ‘serial’, ‘linked’ and ‘convergent attached’, with the first type being the most frequent. Finally, a significant part of the participating dyads display a satisfactory degree of reasoning ‘coherence’, performing their task committed to the main objective of exploring plant growth. Teaching implications of the findings are also discussed.

Data preparation for the computer code FLIRT

Energy Technology Data Exchange (ETDEWEB)

Veale, M E.R.; Wrigley, H E [General Reactor Physics Division, Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)

1964-08-15

The report describes the data preparation for the reactor transient programme FLIRT, and the method of operation of the programme. It includes examples of both input and output for a typical transient calculation. It also includes a section on the numerical techniques used to increase the speed of solution. (author)

Preparation for decommissioning of the Kozloduy Nuclear Power Plant units 1 and 2

International Nuclear Information System (INIS)

Delcheva, T.; Ribarski, V.; Demireva, E.

2006-01-01

The first decommissioning strategy of units 1 and 2 of Kozloduy NPP (KNPP) stipulated 3 phases: a 5 year phase including the post operation activities and preparation of the safe enclosure (SE); a 35 years SE period, followed by deferred dismantling. 'Updated Decommissioning Strategy for Units 1-4 of Kozloduy NPP' was issued in June 2006. The Updated Strategy is based on the so called 'Continuous Dismantling' Concept. The updated Strategy starts preparatory work earlier and then moves into dismantling work without a significant gap. The aim is to achieve a more optimal distribution of the dismantling activities along the time, saving jobs and the existing knowledge of the plant personnel during the decommissioning, and ensuring smooth and more effective use of financial and human resources and of the available infrastructure for waste treatment. This paper gives general information about the updated strategy and activities required for its implementation. (author)

THE IMPROVEMENT OF LOW-WASTE TECHNOLOGIES OF WORKING BODY OF WATER PREPARATION AT THERMAL AND NUCLEAR POWER PLANTS

Directory of Open Access Journals (Sweden)

K. D. Rymasheuskaya

2017-01-01

Full Text Available In the present work the main directions of water desalination technologies improving have been analyzed. Possible techniques of high-quality treatment of water that enable the reduction of amounts of environmentally hazardous substances to be discharged into the hydrosphere are indicated. The purpose of the work was to improve the ecological efficiency and the effectiveness of water treatment equipment at heat power plants when designing new and the modernizing existing water treatment schemes. In order to achieve this goal the following problems have been solved: the one of analyzing the main directions of the improvement of technologies of working body of water preparation at thermal and nuclear power plants; of analyzing the main directions of reduction of total volume of highly mineralized power plant wastewaters; of developing the technological scheme of recycling of concentrate of membrane installations and regenerants of ionite filters in acid and alkali; of developing the technological scheme of transformation of the sludge in pre-processing waste into valuable commodity products. The results of research can be applied for the design of new and the modernization of existing water treatment installations of thermal and nuclear power plants. It will enable to reduce considerably the use of natural water and the amount of chemicals added as well as the volume of wastewater and the concentration of dissolved solids in it. As a consequence, the negative impact of thermal and nuclear power plants on the hydrosphere will be reduced. 

Operation control device for nuclear power plants

International Nuclear Information System (INIS)

Suto, Osamu.

1982-01-01

Purpose: To render the controlling functions of a central control console more centralized by constituting the operation controls for a nuclear power plant with computer systems having substantially independent functions such as those of plant monitor controls, reactor monitor management and CRT display and decreasing interactions between each of the systems. Constitution: An input/output device for the input of process data for a nuclear power plant and indication data for a plant control console is connected to a plant supervisory and control computer system and a display computer system, the plant supervisory control computer system and a reactor and management computer system are connected with a CRT display control device, a printer and a CRT display input/output device, and the display computer system is connected with the CRT display control device and the CRT display unit on the central control console, whereby process input can be processed and displayed at high speed. (Yoshino, Y.)

Interdisciplinary Study of Numerical Methods and Power Plants Engineering

Directory of Open Access Journals (Sweden)

Ioana OPRIS

2014-08-01

Full Text Available The development of technology, electronics and computing opened the way for a cross-disciplinary research that brings benefits by combining the achievements of different fields. To prepare the students for their future interdisciplinary approach,aninterdisciplinary teaching is adopted. This ensures their progress in knowledge, understanding and ability to navigate through different fields. Aiming these results, the Universities introduce new interdisciplinary courses which explore complex problems by studying subjects from different domains. The paper presents a problem encountered in designingpower plants. The method of solvingthe problem isused to explain the numerical methods and to exercise programming.The goal of understanding a numerical algorithm that solves a linear system of equations is achieved by using the knowledge of heat transfer to design the regenerative circuit of a thermal power plant. In this way, the outcomes from the prior courses (mathematics and physics are used to explain a new subject (numerical methods and to advance future ones (power plants.

Large-scale preparation of clove essential oil and eugenol-loaded liposomes using a membrane contactor and a pilot plant.

Science.gov (United States)

Sebaaly, Carine; Greige-Gerges, Hélène; Agusti, Géraldine; Fessi, Hatem; Charcosset, Catherine

2016-01-01

Based on our previous study where optimal conditions were defined to encapsulate clove essential oil (CEO) into liposomes at laboratory scale, we scaled-up the preparation of CEO and eugenol (Eug)-loaded liposomes using a membrane contactor (600 mL) and a pilot plant (3 L) based on the principle of ethanol injection method, both equipped with a Shirasu Porous Glass membrane for injection of the organic phase into the aqueous phase. Homogenous, stable, nanometric-sized and multilamellar liposomes with high phospholipid, Eug loading rates and encapsulation efficiency of CEO components were obtained. Saturation of phospholipids and drug concentration in the organic phase may control the liposome stability. Liposomes loaded with other hydrophobic volatile compounds could be prepared at large scale using the ethanol injection method and a membrane for injection.

PREMOR: a point reactor exposure model computer code for survey analysis of power plant performance

International Nuclear Information System (INIS)

Vondy, D.R.

1979-10-01

The PREMOR computer code was written to exploit a simple, two-group point nuclear reactor power plant model for survey analysis. Up to thirteen actinides, fourteen fission products, and one lumped absorber nuclide density are followed over a reactor history. Successive feed batches are accounted for with provision for from one to twenty batches resident. The effect of exposure of each of the batches to the same neutron flux is determined

PREMOR: a point reactor exposure model computer code for survey analysis of power plant performance

Energy Technology Data Exchange (ETDEWEB)

Vondy, D.R.

1979-10-01

The PREMOR computer code was written to exploit a simple, two-group point nuclear reactor power plant model for survey analysis. Up to thirteen actinides, fourteen fission products, and one lumped absorber nuclide density are followed over a reactor history. Successive feed batches are accounted for with provision for from one to twenty batches resident. The effect of exposure of each of the batches to the same neutron flux is determined.

New Sample Preparation Method for Quantification of Phenolic Compounds of Tea (Camellia sinensis L. Kuntze: A Polyphenol Rich Plant

Directory of Open Access Journals (Sweden)

P. A. Nimal Punyasiri

2015-01-01

Full Text Available Chemical analysis of the Sri Lankan tea (Camellia sinensis, L. germplasm would immensely contribute to the success of the tea breeding programme. However, the polyphenols, particularly catechins (flavan-3-ols, are readily prone to oxidation in the conventional method of sample preparation. Therefore, optimization of the present sample preparation methodology for the profiling of metabolites is much important. Two sample preparation methodologies were compared, fresh leaves (as in the conventional procedures and freeze-dried leaves (a new procedure, for quantification of major metabolites by employing two cultivars, one is known to be high quality black tea and the other low quality black tea. The amounts of major metabolites such as catechins, caffeine, gallic acid, and theobromine, recorded in the new sampling procedure via freeze-dried leaves, were significantly higher than those recorded in the conventional sample preparation procedure. Additionally new method required less amount of leaf sample for analysis of major metabolites and facilitates storage of samples until analysis. The freeze-dried method would be useful for high throughput analysis of large number of samples in shorter period without chemical deterioration starting from the point of harvest until usage. Hence, this method is more suitable for metabolite profiling of tea as well as other phenol rich plants.

Upgrading of Alum Preparation and Dosing Unit for Sharq Dijla Water Treatment Plant by Using Programmable Logic Controller System

Directory of Open Access Journals (Sweden)

Aumar Al-Nakeeb

2018-02-01

Full Text Available One of the important units in Sharq Dijla Water Treatment Plant (WTP first and second extensions are the alum solution preparation and dosing unit. The existing operation of this unit accomplished manually starting from unloading the powder alum in the preparation basin and ending by controlling the alum dosage addition through the dosing pumps to the flash mix chambers. Because of the modern trend of monitoring and control the automatic operation of WTPs due to the great benefits that could be gain from optimum equipment operation, reducing the operating costs and human errors. This study deals with how to transform the conventional operation to an automatic monitoring and controlling system depending on a Programmable Logic Controller (PLC and online sensors for alum preparation and dosing unit in Sharq Dijla WTP. PLC system will receive, analyze transmitting data, compare them with preset points then automatically orders the operational equipment (such as pumps, valves, and mixers in a way that guarantees the safe and appropriate operation of the unit. As a result of Process and Instrumentation Diagrams (PID that were prepared in this study, these units can be fully operating and manage by using Supervisory Control and Data Acquisition (SCADA system.

Computer Education and Computer Use by Preschool Educators

Science.gov (United States)

Towns, Bernadette

2010-01-01

Researchers have found that teachers seldom use computers in the preschool classroom. However, little research has examined why preschool teachers elect not to use computers. This case study focused on identifying whether community colleges that prepare teachers for early childhood education include in their curriculum how teachers can effectively…

Selected bibliography for the extraction of uranium from seawater: chemical process and plant design feasibility study

Energy Technology Data Exchange (ETDEWEB)

Binney, S.E.; Polkinghorne, S.T.; Jante, R.R.; Rodman, M.R.; Chen, A.C.T.; Gordon, L.I.

1979-02-01

A selected annotated bibliography of 521 references was prepared as a part of a feasibility study of the extraction of uranium from seawater. For the most part, these references are related to the chemical processes whereby the uranium is removed from the seawater. A companion docment contains a similar bibliography of 471 references related to oceanographic and uranium extraction plant siting considerations, although some of the references are in common. The bibliography was prepared by computer retrieval from Chemical Abstracts, Nuclear Science Abstracts, Energy Data Base, NTIS, and Oceanic Abstracts. References are listed by author, country of author, and selected keywords.

Selected bibliography for the extraction of uranium from seawater: chemical process and plant design feasibility study

International Nuclear Information System (INIS)

Binney, S.E.; Polkinghorne, S.T.; Jante, R.R.; Rodman, M.R.; Chen, A.C.T.; Gordon, L.I.

1979-02-01

A selected annotated bibliography of 521 references was prepared as a part of a feasibility study of the extraction of uranium from seawater. For the most part, these references are related to the chemical processes whereby the uranium is removed from the seawater. A companion docment contains a similar bibliography of 471 references related to oceanographic and uranium extraction plant siting considerations, although some of the references are in common. The bibliography was prepared by computer retrieval from Chemical Abstracts, Nuclear Science Abstracts, Energy Data Base, NTIS, and Oceanic Abstracts. References are listed by author, country of author, and selected keywords

Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

International Nuclear Information System (INIS)

Hou, Xue Yan; Li, Shu; Li, Qing

2011-01-01

Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier

IAEA activities to prepare safety codes and guides for thermal neutron nuclear power plants

International Nuclear Information System (INIS)

Iansiti, E.

1977-01-01

In accordance with the programme presented to, and endorsed by, the eighteenth General Conference in September 1974, the IAEA is now developing a complete set of safety codes and guides that will represent recommendations for the safety of thermal neutron power plants. The safety codes outline the minimum requirements for achieving this safety, and the safety guides set forth the criteria, procedures and methods to implement the safety codes. The whole programme is directed towards the five areas of Governmental Organization, Siting, Design, Operation, and Quality Assurance. One Scientific Secretary from the Agency Secretariat is responsible for each of these areas and a Co-ordinator takes care of common problems. For the development of each of these documents a working group of a few world experts is first convened which prepare a preliminary draft. This draft is then reviewed by a larger, international Technical Review Committee (one for each of the five areas) and a subsequent review by the Senior Advisory Group - with representatives from 20 states - ensures that the document is well coordinated within the programme. At this stage, it is sent to Member States for comments. The Technical Review Committee concerned is reconvened to integrate these comments into the document, and, after a final review by the Senior Advisory Group, the document is ready for transmission to the Director General of the Agency for endorsement and publication. A preliminary to this procedure is the collation by the Secretariat of large amounts of information submitted by Member States so that the first draft is really based on a very complete knowledge of what is done in each area all over the world. This collation frequently reveals differences in approach which are not random but due, rather, to the local conditions and the types of reactors. These differences must be harmonized in the documents produced without detracting from the effectiveness of the code or guide. The whole

WIPP conceptual design report. Addendum M. Computer system and data processing requirements for Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Young, R.

1977-06-01

Data-processing requirements for the Waste Isolation Pilot Plant (WIPP) dictate a computing system that can provide a wide spectrum of data-processing needs on a 24-hour-day basis over an indeterminate time. A computer system is defined as a computer or computers complete with all peripheral equipment and extensive software and communications capabilities, including an operating system, compilers, assemblers, loaders, etc., all applicable to real-world problems. The computing system must be extremely reliable and easily expandable in both hardware and software to provide for future capabilities with a minimum impact on the existing applications software and operating system. The computer manufacturer or WIPP operating contractor must provide continuous on-site computer maintenance (maintain an adequate inventory of spare components and parts to guarantee a minimum mean-time-to-repair of any portion of the computer system). The computer operating system or monitor must process a wide mix of application programs and languages, yet be readily changeable to obtain maximum computer usage. The WIPP computing system must handle three general types of data processing requirements: batch, interactive, and real-time. These are discussed. Data bases, data collection systems, scientific and business systems, building and facilities, remote terminals and locations, and cables are also discussed

3D - Acquisition systems - test in Chooz B nuclear plant

International Nuclear Information System (INIS)

Brillault, B.; Thibault, G.

1992-06-01

EDF needs 3D-acquisition systems to get the precise geometry of critical nuclear spaces in order to prepare computer simulations of operations in these areas. The simulations must lead to an increase of the efficiency of the operation. The acquisition of the 3-D geometry can be done using 3D-acquisition systems. To answer the needs of the Construction Division, four different systems are compared by the Research Division in Chooz B nuclear plant in order to determine the right solution for each 3D-acquisition problem

Dukovany ASSET mission preparation

International Nuclear Information System (INIS)

Kouklik, I.

1996-01-01

We are in the final stages of the Dukovany ASSET mission 1996 preparation. I would like to present some of our recent experiences. Maybe they would be helpful to other plants, that host ASSET missions in future

Dukovany ASSET mission preparation

Energy Technology Data Exchange (ETDEWEB)

Kouklik, I [NPP Dukovany (Czech Republic)

1997-12-31

We are in the final stages of the Dukovany ASSET mission 1996 preparation. I would like to present some of our recent experiences. Maybe they would be helpful to other plants, that host ASSET missions in future.

Influence of Heat Treatment of Nickel-Titanium Rotary Endodontic Instruments on Apical Preparation: A Micro-Computed Tomographic Study.

Science.gov (United States)

de Almeida, Bernardo Corrêa; Ormiga, Fabíola; de Araújo, Marcos César Pimenta; Lopes, Ricardo Tadeu; Lima, Inayá Corrêa Barbosa; dos Santos, Bernardo Camargo; Gusman, Heloisa

2015-12-01

The aim of this study was to make a 3-dimensional comparison of the canal transportation and changes in apical geometry using micro-computed tomographic imaging after canal preparation with K3 (SybronEndo, Orange, CA) and K3XF (SybronEndo) file systems. Twenty-eight mandibular molars were randomly divided into 2 groups according to the rotary system used in instrumentation: K3 or K3XF. The specimens were scanned by micro-computed tomographic imaging before and after instrumentation. Images before and after instrumentation from each group were compared with regard to canal volume, surface area, and structure model index (SMI) (paired t test, P instrumentation, the canals from each group were compared regarding the changes in volume, surface area, SMI, and canal transportation in the last 4 apical mm (t test, P Instrumentation with the 2 rotary systems significantly changed the canal volume, surface area, and SMI (P instrument types concerning these parameters (P > .05). There were no significant differences between the 2 groups with regard to canal transportation in the last 4 apical mm (P > .05). Both rotary systems showed adequate canal preparations with reduced values of canal transportation. Heat treatment did not influence changes in root canal geometry in the apical region. Copyright © 2015 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

Direct linear measurement of root dentin thickness and dentin volume changes with post space preparation: A cone-beam computed tomography study

Directory of Open Access Journals (Sweden)

Shoeb Yakub Shaikh

2018-01-01

Full Text Available Aim: The purpose of the present study was direct linear measurement of dentin thickness and dentin volume changes for post space preparation with cone-beam computed tomography (CBCT. Materials and Methods: Ten maxillary central incisors were scanned, before and after root canal and post space preparation, with Orthophos XG three-dimensional hybrid unit. Thirteen axial section scans of each tooth from orifice to apex and dentin thickness for buccal, lingual, mesial, and distal were measured using proprietary measuring tool and thereafter subjected to statistical analysis. Furthermore, dentin volume was evaluated using ITK-SNAP software. Results: There was statistically significant difference between the dentin thickness in pre- and postinstrumentation (paired t-test and also between different groups (one-way ANOVA. In the shortest post length of 4.5mm the post space preparation resulted in 2.17% loss of hard tissue volume, where as 11mm longest post length post space preparation resulted in >40% loss of hard tissue volume. Conclusion: CBCT axial section scan for direct measurements of root dentin thickness can be guideline before and after post space preparation for selection of drill length and diameter.

Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

2005-04-01

Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

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

Computer simulations of discharges from a lignite power plant complex

International Nuclear Information System (INIS)

Koukouliou, V.; Horyna, J.; Perez-Sanchez, D.

2008-01-01

This paper describes work carried out within the IAEA EMRAS program NORM working group to test the predictions of three computer models against measured radionuclide concentrations resulting from discharges from a lignite power plant complex. This complex consists of two power plants with a total of five discharge stacks, situated approximately 2-5 kilometres from a city of approximately 10,000 inhabitants. Monthly measurements of mean wind speed and direction, dust loading, and 238 U activities in fallout samples, as well as mean annual values of 232 Th activity in the nearest city sampling sites were available for the study. The models used in the study were Pc-CREAM (a detailed impact assessment model), and COMPLY and CROM (screening models). In applying the models to this scenario it was noted that the meteorological data provided was not ideal for testing, and that a number of assumptions had to be made, particularly for the simpler models. However, taking the gaps and uncertainties in the data into account, the model predictions from PC-CREAM were generally in good agreement with the measured data, and the results from different models were also generally consistent with each other. However, the COMPLY predictions were generally lower than those from PC-CREAM. This is of concern, as the aim of a screening model (COMPLY) is to provide conservative estimates of contaminant concentrations. Further investigation of this problem is required. The general implications of the results for further model development are discussed. (author)

Computer simulation of black out followed by multiple failures in PWR type nuclear power plants

International Nuclear Information System (INIS)

Silva Filho, E.

1989-01-01

The computer code RELAP 5/MOD 1 has been utilized to investigate the thermal-hydraulic behaviour of a standard 1300 MWe pressurized water reactor plant of the KWU design during a station blackout following a inadequate performance of the pressurizer and steam generator safety valves. During the simulation the reactor scram system the emergency coolant system of the primary loop and the emergency Feedwater system of the secondary loop are considered inactive. (author) [pt

New classification of operators' human errors at overseas nuclear power plants and preparation of easy-to-use case sheets

International Nuclear Information System (INIS)

Takagawa, Kenichi

2004-01-01

At nuclear power plants, plant operators examine other human error cases, including those that occurred at other plants, so that they can learn from such experiences and avoid making similar errors again. Although there is little data available on errors made at domestic plants, nuclear operators in foreign countries are reporting even minor irregularities and signs of faults, and a large amount of data on human errors at overseas plants could be collected and examined. However, these overseas data have not been used effectively because most of them are poorly organized or not properly classified and are often hard to understand. Accordingly, we carried out a study on the cases of human errors at overseas power plants in order to help plant personnel clearly understand overseas experiences and avoid repeating similar errors, The study produced the following results, which were put to use at nuclear power plants and other facilities. (1) ''One-Point-Advice'' refers to a practice where a leader gives pieces of advice to his team of operators in order to prevent human errors before starting work. Based on this practice and those used in the aviation industry, we have developed a new method of classifying human errors that consists of four basic actions and three applied actions. (2) We used this new classification method to classify human errors made by operators at overseas nuclear power plants. The results show that the most frequent errors caused not by operators themselves but due to insufficient team monitoring, for which superiors and/or their colleagues were responsible. We therefore analyzed and classified possible factors contributing to insufficient team monitoring, and demonstrated that the frequent errors have also occurred at domestic power plants. (3) Using the new classification formula, we prepared a human error case sheets that is easy for plant personnel to understand. The sheets are designed to make data more understandable and easier to remember

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...

Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

Energy Technology Data Exchange (ETDEWEB)

Hou, Xue Yan; Li, Shu; Li, Qing [China Nuclear Power Operation Technology Co., Wuhan (China)

2011-08-15

Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier.

A computer based I and C to improve nuclear power plant operation and safety

International Nuclear Information System (INIS)

Appell, Bernard; Beltranda, Guy

1995-01-01

Chooz B1 is the head of 1400 MW N4 series (up to now, a programme of 4 identical units have been ordered) will be put on the French national grid this year (1995). Hot tests were performed last autumn. Loading fuel is scheduled in June 95. Chooz B2 will follow 6 months later. This nuclear power plant series is fully French designed. It comprises, compared to the former 1300 MW series, evolution concerning mainly the turbine, the steam generators, the primary pumps, the I and C and the man machine interface. A major improvement for the plant operation and safety is the computerised I and C which comprises the protection system (specific controllers), the process automation system (off the shelf equipment), the computer based and conventional man machine interfaces associated. These systems were put in service last year. This paper is focused on them. (author)

Advanced computer-based training

Energy Technology Data Exchange (ETDEWEB)

Fischer, H D; Martin, H D

1987-05-01

The paper presents new techniques of computer-based training for personnel of nuclear power plants. Training on full-scope simulators is further increased by use of dedicated computer-based equipment. An interactive communication system runs on a personal computer linked to a video disc; a part-task simulator runs on 32 bit process computers and shows two versions: as functional trainer or as on-line predictor with an interactive learning system (OPAL), which may be well-tailored to a specific nuclear power plant. The common goal of both develoments is the optimization of the cost-benefit ratio for training and equipment.

Advanced computer-based training

International Nuclear Information System (INIS)

Fischer, H.D.; Martin, H.D.

1987-01-01

The paper presents new techniques of computer-based training for personnel of nuclear power plants. Training on full-scope simulators is further increased by use of dedicated computer-based equipment. An interactive communication system runs on a personal computer linked to a video disc; a part-task simulator runs on 32 bit process computers and shows two versions: as functional trainer or as on-line predictor with an interactive learning system (OPAL), which may be well-tailored to a specific nuclear power plant. The common goal of both develoments is the optimization of the cost-benefit ratio for training and equipment. (orig.) [de

Effect of Post Space Preparation on Apical Obturation Quality of Teeth Obturated with Different Techniques: A Micro-computed Tomographic Study.

Science.gov (United States)

Küçükkaya Eren, Selen; Askerbeyli Örs, Sevinc; Yılmaz, Zeliha

2017-07-01

The purpose of this study was to evaluate the obturation quality of root canals filled with different techniques and to determine whether post space preparation had an effect on the quality of apical obturation using micro-computed tomographic (micro-CT) imaging. The root canals of 30 human mandibular premolar teeth were instrumented, and the specimens were divided into 3 groups according to the obturation technique used: cold lateral compaction (CLC), warm vertical compaction (WVC), or single-cone (SC) techniques. The specimens were stored at 37°C and 100% humidity for 1 week. Then, the coronal root filling material was removed in order to create a post space. Micro-CT scans were performed before and after post space preparation for the volumetric analysis of voids and filling materials. Data were analyzed using repeated-measures analysis of variance and Bonferroni tests. The CLC and SC groups showed a significantly greater percentage volume of voids than the WVC group (P space preparation (P > .05). The post space preparation caused a significant increase in the percentage volume of voids in the CLC and SC groups (P space preparation (P > .05). No root fillings were void free. The WVC group presented the best obturation quality. The post space preparation negatively influenced the apical integrity of the filling materials in the CLC and SC groups, whereas it had no significant effect in the WVC group. Copyright © 2017 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

STAR-concept: method for the definition and generation of computer-based systems to support the operator during normal and disturbed plant situations

International Nuclear Information System (INIS)

Felkel, L.; Roggenbauer, H.

1983-01-01

The paper describes a variety of functions to improve man-machine communication in nuclear power plants by advanced use of process computers. Special functions of interest here are: computerized operational manual; post trip analysis; alarm reduction; disturbance analysis and surveillance; and improved plant information processing, retrieval and display. All these functions use complex combinations of plant signals. The combinations (discrete process models) have to be described in a homogenous and formal way. The methodology used as well as the functions and examples are given. Experience from a pilot application in a nuclear power plant is also reported

Enhancement of Operating Efficiency Of The Central Coal-Preparation Plant of "MMK - UGOL" Ltd. Under Current Conditions

Science.gov (United States)

Basarygin, Maksim

2017-11-01

In this article the subject of enhancement of operating efficiency of the central coal-preparation plant of OOO "MMK-UGOL" is encompassed. Modern trends in the development of technologies and equipment for coal beneficiation are due to the following requirements: improving competitiveness of coal products, improvement of quality of marketable products, reduction of coal production cost, environmental requirements: polluting emission abatement, prepared coal saving, improvement of the effectiveness of resource conservation; complex mechanization and beneficiation process automation. In the article the contemporary problems of raw coal benefication under current conditions of the increased dilution of withdrawable coals with rock fractions are considered. Comparative analysis of efficiency of application of modern concentrating equipment under the conditions of the CCPP of OOO "MMK-UGOL" is carried out on the basis of research works. Particular attention is paid to dehydration of produced coal concentrate with content of volatile agents of more than 35.0% and content of fine-dispersed particles in flotation concentrate of more than 50.0%. Comparative analysis of the coal concentrate dehydration technologies is conducted.

Parallel quantum computing in a single ensemble quantum computer

International Nuclear Information System (INIS)

Long Guilu; Xiao, L.

2004-01-01

We propose a parallel quantum computing mode for ensemble quantum computer. In this mode, some qubits are in pure states while other qubits are in mixed states. It enables a single ensemble quantum computer to perform 'single-instruction-multidata' type of parallel computation. Parallel quantum computing can provide additional speedup in Grover's algorithm and Shor's algorithm. In addition, it also makes a fuller use of qubit resources in an ensemble quantum computer. As a result, some qubits discarded in the preparation of an effective pure state in the Schulman-Varizani and the Cleve-DiVincenzo algorithms can be reutilized

Project subsidized by the Sunshine Project in fiscal 1982. Report on achievements in the project commissioned from NEDO - development of a hot water utilizing power generation plant and development of a binary cycle power generation plant (Researches on corrosion preventive measures and the cycle optimum for the plant); 1982 nendo nessui riyo hatsuden plant no kaihatsu seika hokokusho. Binary cycle hatsuden plant no kaihatsu (fushoku taisaku no kenkyu oyobi plant saiteki cycle no kenkyu)

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-03-01

As the element research on a 10-MW class geothermal binary cycle power plant to be built in the coming term, researches were made on corrosion preventive measures and the cycle optimum for the plant. This paper reports the achievements in fiscal 1982. In the research on corrosion preventive measures, different kinds of materials were buried in three locations having different soil natures to study corrosion due to soil. The corrosion rate of heat conducting pipes using the heat media R114 was estimated as very small as 1/40 of the corrosion rate in geothermal waters. In the research on the cycle optimum for the plant, experimental research was performed on thermo-dynamic properties and thermal stability of the mixed media using R114 as the main component. As a result, the R114/R112 system was found to have higher pressure than R114, but the media circulation amount is less, and the output at the power transmission terminal increased by 5 to 10%. The system showed the most excellent heat cycle characteristics. In the research of building a power plant installed with two different power generation systems, a computer program was prepared that calculates heat balances all at once for the case of installing a geothermal binary cycle power plant in a geothermal steam power plant. (NEDO)

Investigation of CPD and HMDS Sample Preparation Techniques for Cervical Cells in Developing Computer-Aided Screening System Based on FE-SEM/EDX

Science.gov (United States)

Ng, Siew Cheok; Abu Osman, Noor Azuan

2014-01-01

This paper investigated the effects of critical-point drying (CPD) and hexamethyldisilazane (HMDS) sample preparation techniques for cervical cells on field emission scanning electron microscopy and energy dispersive X-ray (FE-SEM/EDX). We investigated the visualization of cervical cell image and elemental distribution on the cervical cell for two techniques of sample preparation. Using FE-SEM/EDX, the cervical cell images are captured and the cell element compositions are extracted for both sample preparation techniques. Cervical cell image quality, elemental composition, and processing time are considered for comparison of performances. Qualitatively, FE-SEM image based on HMDS preparation technique has better image quality than CPD technique in terms of degree of spread cell on the specimen and morphologic signs of cell deteriorations (i.e., existence of plate and pellet drying artifacts and membrane blebs). Quantitatively, with mapping and line scanning EDX analysis, carbon and oxygen element compositions in HMDS technique were higher than the CPD technique in terms of weight percentages. The HMDS technique has shorter processing time than the CPD technique. The results indicate that FE-SEM imaging, elemental composition, and processing time for sample preparation with the HMDS technique were better than CPD technique for cervical cell preparation technique for developing computer-aided screening system. PMID:25610902

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

Energy Technology Data Exchange (ETDEWEB)

Duran, Felicia Angelica [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.; Waymire, Russell L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.

2013-10-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

International Nuclear Information System (INIS)

Duran, Felicia Angelica; Waymire, Russell L.

2013-01-01

Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

[Medicinal preparations in Mattioli's herbarium of 1596].

Science.gov (United States)

Drabek, P

2008-06-01

Herbaria in the 16th century very often included also the information concerning the use of medicinal plants in practice. The second Czech edition of Mattioli's Herbarium presented about 4000 pieces of therapeutic advice and instructions, including nearly 200 complete prescriptions for medicinal preparations. Preparations for internal use were mainly potions and concoctions. In preparations for external administration, the dosage was not of great importance and therefore less attention was paid to their precise composition. At that period, distillation was still widely used to prepare medicaments.

TOSHIBA CAE system for nuclear power plant

International Nuclear Information System (INIS)

Machiba, Hiroshi; Sasaki, Norio

1990-01-01

TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

Prognostics and health management system for hydropower plant based on fog computing and docker container

Science.gov (United States)

Xiao, Jian; Zhang, Mingqiang; Tian, Haiping; Huang, Bo; Fu, Wenlong

2018-02-01

In this paper, a novel prognostics and health management system architecture for hydropower plant equipment was proposed based on fog computing and Docker container. We employed the fog node to improve the real-time processing ability of improving the cloud architecture-based prognostics and health management system and overcome the problems of long delay time, network congestion and so on. Then Storm-based stream processing of fog node was present and could calculate the health index in the edge of network. Moreover, the distributed micros-service and Docker container architecture of hydropower plants equipment prognostics and health management was also proposed. Using the micro service architecture proposed in this paper, the hydropower unit can achieve the goal of the business intercommunication and seamless integration of different equipment and different manufacturers. Finally a real application case is given in this paper.

Preparation of functions of computer code GENGTC and improvement for two-dimensional heat transfer calculations for irradiation capsules

International Nuclear Information System (INIS)

Nomura, Yasushi; Someya, Hiroyuki; Ito, Haruhiko.

1992-11-01

Capsules for irradiation tests in the JMTR (Japan Materials Testing Reactor), consist of irradiation specimens surrounded by a cladding tube, holders, an inner tube and a container tube (from 30mm to 65mm in diameter). And the annular gaps between these structural materials in the capsule are filled with liquids or gases. Cooling of the capsule is done by reactor primary coolant flowing down outside the capsule. Most of the heat generated by fission in fuel specimens and gamma absorption in structural materials is directed radially to the capsule container outer surface. In thermal performance calculations for capsule design, an one(r)-dimensional heat transfer computer code entitled (Generalyzed Gap Temperature Calculation), GENGTC, originally developed in Oak Ridge National Laboratory, U.S.A., has been frequently used. In designing a capsule, are needed many cases of parametric calculations with respect to changes materials and gap sizes. And in some cases, two(r,z)-dimensional heat transfer calculations are needed for irradiation test capsules with short length fuel rods. Recently the authors improved the original one-dimensional code GENGTC, (1) to simplify preparation of input data, (2) to perform automatic calculations for parametric survey based on design temperatures, ect. Moreover, the computer code has been improved to perform r-z two-dimensional heat transfer calculation. This report describes contents of the preparation of the one-dimensional code GENGTC and the improvement for the two-dimensional code GENGTC-2, together with their code manuals. (author)

A Microbiological Preparation Based on the Homofermentative Strains of Lactobacillus plantarum Isolated from the Natural Sources for Bioconservation of Plant Resources (Review of Studies between 2000 and 2015

Directory of Open Access Journals (Sweden)

R.A. Shurkhno

2016-03-01

Full Text Available The paper reviews studies performed by the author for improving the process of bioconservation of plant resources by creating an effective microbiological preparation based on the active strains of lactic acid bacteria. It is known that the problem of production of biological preservatives can be solved by using the basic principles of microbiological and biotechnological processes that contribute to the creation of biological preservatives ensuring the most optimal and efficient fermentation of plant mass, i.e., by using homofermentative lactic acid bacteria (Lactobacillus plantarum isolated from the natural ecological niches, as well as by conservation of plant mass with the help of lactic acid bacteria at the stage of high physiological activity. In view of the above features, а microbial preparation “Universal Silage Ferment – BIOAGRO” was developed on the basis of two new strains of Lactobacillus plantarum RS3 and L. plantarum RS4, both isolated from natural sources, and implemented in the industrial production. Indus-trial introduction and testing of the microbiological preparation was carried out for 3 years (2012–2014 in ten farms of eight districts of the Republic of Tatarstan (Russia. It was found that the use of the preparation along with an optimized technology of bioconservation of high-protein perennials, annual grasses, their mixtures and corn, and slightly dried herbs in anaerobic conditions improves the qualitative characteristics of silage and haylage, as well as increases their energy value and enhances the economic performance of technological processes of fodder conservation.

Computer aid in rescue organisation on site in case of catastrophic situation on nuclear plant

International Nuclear Information System (INIS)

Teissier, M.

1992-01-01

The rescue organisation in case of catastrophic situation is based on known principles: creation of medical buffer structures between hazard spot where injured people are being collected and rear hospitals, triage of victims as urgent casualties. We will propose computer aid in order to value the time used to prepare and evacuate all the victims from the site, knowing inventory of available means, waiting periods and lengths of intervention, types and number of victims. Thus, it is possible to optimize the former organisation, qualitatively and quantitatively to improve efficiency in rescuing operations. (author)

Using a Praxeology Approach to the Rational Choice of Specialized Software in the Preparation of the Computer Science Teacher

Directory of Open Access Journals (Sweden)

Elena Semenikhina

2018-02-01

Full Text Available From the positions of Praxeology, the aspects of the forming of the future teachers’ abilities to choose software that turns out to be the most rational for the solving of the professional task are considered in the article (on the example of computer science teachers’ preparation to use dynamic mathematics software (DMS. The forming of such abilities based on a formula "one task – different software" is described. The methodology of organization of such experimental studies on the base of Sumy State Pedagogical University (Ukraine is described. The results of the statistical analysis of data are given on the basis of non-parametric sign test for dependent sample. It is educed that taking into account such approach provides the positive dynamics of the level of future informatics teachers’ preparation at the significance level of 0.05.

The Marstal Central Solar Heating Plant

DEFF Research Database (Denmark)

Heller, Alfred; Jochen, Dahm

1999-01-01

The central solar heating plant in Marstal is running since 1996 and has been monitored since. The resulting data from the plant is analysed and the plant performance evaluated. A TRNSYS-model (computersimulation) id prepared and validated based on the measured data from the plant. Acceptable good...

Micro-computed Tomographic Analysis of Apical Microcracks before and after Root Canal Preparation by Hand, Rotary, and Reciprocating Instruments at Different Working Lengths.

Science.gov (United States)

de Oliveira, Bruna Paloma; Câmara, Andréa Cruz; Duarte, Daniel Amancio; Heck, Richard John; Antonino, Antonio Celso Dantas; Aguiar, Carlos Menezes

2017-07-01

This study aimed to compare apical microcrack formation after root canal shaping by hand, rotary, and reciprocating files at different working lengths using micro-computed tomographic analysis. Sixty mandibular incisors were randomly divided into 6 experimental groups (n = 10) according to the systems and working lengths used for the root canal preparation: ProTaper Universal for Hand Use (Dentsply Maillefer, Ballaigues, Switzerland), HyFlex CM (Coltene-Whaledent, Allstetten, Switzerland), and Reciproc (VDW, Munich, Germany) files working at the apical foramen (AF) and 1 mm short of the AF (AF - 1 mm). The teeth were imaged with micro-computed tomographic scanning at an isotropic resolution of 14 μm before and after root canal preparation, and the cross-sectional images generated were assessed to detect microcracks in the apical portion of the roots. Overall, 17 (28.3%) specimens presented microcracks before instrumentation. Apical microcracks were present in 1 (ProTaper Universal for Hand Use), 3 (Hyflex CM), and 2 (Reciproc) specimens when the instrumentation terminated at the AF. When instrumentation was terminated at AF - 1 mm, apical microcracks were detected in 3 (ProTaper Universal for Hand Use) and 4 (Hyflex CM and Reciproc) specimens. All these microcracks detected after root canal preparation were already present before instrumentation, and no new apical microcrack was visualized. For all groups, the number of slices presenting microcracks after root canal preparation was the same as before canal preparation. Root canal shaping with ProTaper Universal for Hand Use, HyFlex CM, and Reciproc systems, regardless of the working length, did not produce apical microcracks. Copyright © 2017 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

Analog and hybrid computing

CERN Document Server

Hyndman, D E

2013-01-01

Analog and Hybrid Computing focuses on the operations of analog and hybrid computers. The book first outlines the history of computing devices that influenced the creation of analog and digital computers. The types of problems to be solved on computers, computing systems, and digital computers are discussed. The text looks at the theory and operation of electronic analog computers, including linear and non-linear computing units and use of analog computers as operational amplifiers. The monograph examines the preparation of problems to be deciphered on computers. Flow diagrams, methods of ampl

Computer code development plant for SMART design

International Nuclear Information System (INIS)

Bae, Kyoo Hwan; Choi, S.; Cho, B.H.; Kim, K.K.; Lee, J.C.; Kim, J.P.; Kim, J.H.; Chung, M.; Kang, D.J.; Chang, M.H.

1999-03-01

In accordance with the localization plan for the nuclear reactor design driven since the middle of 1980s, various computer codes have been transferred into the korea nuclear industry through the technical transfer program from the worldwide major pressurized water reactor supplier or through the international code development program. These computer codes have been successfully utilized in reactor and reload core design works. As the results, design- related technologies have been satisfactorily accumulated. However, the activities for the native code development activities to substitute the some important computer codes of which usages are limited by the original technique owners have been carried out rather poorly. Thus, it is most preferentially required to secure the native techniques on the computer code package and analysis methodology in order to establish the capability required for the independent design of our own model of reactor. Moreover, differently from the large capacity loop-type commercial reactors, SMART (SYSTEM-integrated Modular Advanced ReacTor) design adopts a single reactor pressure vessel containing the major primary components and has peculiar design characteristics such as self-controlled gas pressurizer, helical steam generator, passive residual heat removal system, etc. Considering those peculiar design characteristics for SMART, part of design can be performed with the computer codes used for the loop-type commercial reactor design. However, most of those computer codes are not directly applicable to the design of an integral reactor such as SMART. Thus, they should be modified to deal with the peculiar design characteristics of SMART. In addition to the modification efforts, various codes should be developed in several design area. Furthermore, modified or newly developed codes should be verified their reliability through the benchmarking or the test for the object design. Thus, it is necessary to proceed the design according to the

Computer code development plant for SMART design

Energy Technology Data Exchange (ETDEWEB)

Bae, Kyoo Hwan; Choi, S.; Cho, B.H.; Kim, K.K.; Lee, J.C.; Kim, J.P.; Kim, J.H.; Chung, M.; Kang, D.J.; Chang, M.H

1999-03-01

In accordance with the localization plan for the nuclear reactor design driven since the middle of 1980s, various computer codes have been transferred into the korea nuclear industry through the technical transfer program from the worldwide major pressurized water reactor supplier or through the international code development program. These computer codes have been successfully utilized in reactor and reload core design works. As the results, design- related technologies have been satisfactorily accumulated. However, the activities for the native code development activities to substitute the some important computer codes of which usages are limited by the original technique owners have been carried out rather poorly. Thus, it is most preferentially required to secure the native techniques on the computer code package and analysis methodology in order to establish the capability required for the independent design of our own model of reactor. Moreover, differently from the large capacity loop-type commercial reactors, SMART (SYSTEM-integrated Modular Advanced ReacTor) design adopts a single reactor pressure vessel containing the major primary components and has peculiar design characteristics such as self-controlled gas pressurizer, helical steam generator, passive residual heat removal system, etc. Considering those peculiar design characteristics for SMART, part of design can be performed with the computer codes used for the loop-type commercial reactor design. However, most of those computer codes are not directly applicable to the design of an integral reactor such as SMART. Thus, they should be modified to deal with the peculiar design characteristics of SMART. In addition to the modification efforts, various codes should be developed in several design area. Furthermore, modified or newly developed codes should be verified their reliability through the benchmarking or the test for the object design. Thus, it is necessary to proceed the design according to the

Analyses of transient plant response under emergency situations

Energy Technology Data Exchange (ETDEWEB)

Koyama, Kazuya [Advanced Reactor Technology, Co. Ltd., Engineering Department, Tokyo (Japan); Shimakawa, Yoshio; Hishida, Masahiko [Mitsubishi Heavy Industry, Ltd., Reactor Core Engineering and Safety Engineering Department, Tokyo (Japan)

1999-03-01

In order to support development of the dynamic reliability analysis program DYANA, analyses were made on the event sequences anticipated under emergency situations using the plant dynamics simulation computer code Super-COPD. The analytical models were developed for Super-COPD such as the guard vessel, the maintenance cooling system, the sodium overflow and makeup system, etc. in order to apply the code to the simulation of the emergency situations. The input data were prepared for the analyses. About 70 sequences were analyzed, which are categorized into the following events: (1) PLOHS (Protected Loss of Heat Sink), (2) LORL (Loss of Reactor Level)-J: failure of sodium makeup by the primary sodium overflow and makeup system, (3) LORL-G : failure of primary coolant pump trip, (4) LORL-I: failure of the argon cover gas isolation, and (5) heat removal only using the ventilation system of the primary cooling system rooms. The results were integrated into an input file for preparing the functions for the neural network simulation. (author)

Science assessment of fusion power plant

International Nuclear Information System (INIS)

Nagai, Toru; Shimazu, Yasuo

1984-01-01

A concept of SCIENCE ASSESSMENT (SA) is proposed to support a research program of the so-called big science. The SA System should be established before the demonstration reactor is realized, and the system is classified into four categories: (1) Resource Economy Assessment (REA) (cost evaluation and availability of rare resource materials), (2) Risk Assessment (RA) (structural safety during operation and accident), (3) Environmental Assessment (EA) (adaptability to environments), and (4) Socio-Political Assessment (SPA) (from local public acceptance to national policy acceptance). Here, REA to the published conceptual designs of commercial fusion power plants (most of them are TOKAMAK) is carried out as the first step. The energy analysis method is imployed because the final goal of fusion plant is to supply energy. The evaluation index is the energy ratio (= output/input). Computer code for energy analysis was developed, to which the material inventory table from the conceptual design and the database for the energy intensity (= energy required to obtain a unit amount of materials) were prepared. (Nogami, K.)

The plant-window system

International Nuclear Information System (INIS)

Wood, R.T.; Mullens, J.A.; Naser, J.A.

1995-01-01

Power plant data, and the information that can be derived from it, provide the link to the plant through which the operations, maintenance and engineering staff understand and manage plant performance. The increasing use of computer technology in the U.S. nuclear power industry has greatly expanded the capability to obtain, analyze, and present data about the plant to station personnel. However, it is necessary to transform the vast quantity of available data into clear, concise, and coherent information that can be readily accessed and used throughout the plant. This need can be met by an integrated computer workstation environment that provides the necessary information and software applications, in a manner that can be easily understood and used, to the proper users throughout the plant. As part of a Cooperative Research and Development Agreement with the Electric Power Research Institute, the Oak Ridge National Laboratory has developed functional requirements for a Plant-Wide Integrated Environment Distributed On Workstations (Plant-Window) System. The Plant-Window System (PWS) can serve the needs of operations, engineering, and maintenance personnel at nuclear power stations by providing integrated data and software applications (e.g., monitoring, analysis, diagnosis, and control applications) within a common environment. The PWS requirements identify functional capabilities and provide guidelines for standardized hardware, software, and display interfaces to define a flexible computer environment that permits a tailored implementation of workstation capabilities and facilitates future upgrades

PRIMUS: a computer code for the preparation of radionuclide ingrowth matrices from user-specified sources

International Nuclear Information System (INIS)

Hermann, O.W.; Baes, C.F. III; Miller, C.W.; Begovich, C.L.; Sjoreen, A.L.

1984-10-01

The computer program, PRIMUS, reads a library of radionuclide branching fractions and half-lives and constructs a decay-chain data library and a problem-specific decay-chain data file. PRIMUS reads the decay data compiled for 496 nuclides from the Evaluated Nuclear Structure Data File (ENSDF). The ease of adding radionuclides to the input library allows the CRRIS system to further expand its comprehensive data base. The decay-chain library produced is input to the ANEMOS code. Also, PRIMUS produces a data set reduced to only the decay chains required in a particular problem, for input to the SUMIT, TERRA, MLSOIL, and ANDROS codes. Air concentrations and deposition rates from the PRIMUS decay-chain data file. Source term data may be entered directly to PRIMUS to be read by MLSOIL, TERRA, and ANDROS. The decay-chain data prepared by PRIMUS is needed for a matrix-operator method that computes either time-dependent decay products from an initial concentration generated from a constant input source. This document describes the input requirements and the output obtained. Also, sections are included on methods, applications, subroutines, and sample cases. A short appendix indicates a method of utilizing PRIMUS and the associated decay subroutines from TERRA or ANDROS for applications to other decay problems. 18 references

Separation of krypton from dissolver off-gas of a reprocessing plant using preparative gas chromatography

International Nuclear Information System (INIS)

Matoni, M.

1984-02-01

Kr-85 can be separated from the pre-purified purge air in the final processing step of the purification phase for dissolver off-gases of a reprocessing plant with the aid of preparative gas chromatography. Activated carbon adsorbers in combination with helium as carrier gas permits maximum gas mixture through-flow. A separation temperature of 30 0 C is considered optimal. An adsorbent volume of 40 dm 3 is necessary for processing the residual gas flow of 2.5 Nm 3 /h; the adsorbent is divided between 2 columns linked in series each of which are 2 m long with an internal diameter of 100 mm. The helium flow required is five times greater than the off-gas flow. The degree of purity for krypton is greater than 90% for a decontamination factor of greater than 1000. (orig./HP) [de

Savannah River Plant's Accountability Inventory Management System (AIMS) (Nuclear materials inventory control)

International Nuclear Information System (INIS)

Croom, R.G.

1976-06-01

The Accountability Inventory Management System (AIMS) is a new computer inventory control system for nuclear materials at the Savannah River Plant, Aiken, South Carolina. The system has two major components, inventory files and system parameter files. AIMS, part of the overall safeguards program, maintains an up-to-date record of nuclear material by location, produces reports required by ERDA in addition to onplant reports, and is capable of a wide range of response to changing input/output requirements through use of user-prepared parameter cards, as opposed to basic system reprogramming

Generalized fish life-cycle poplulation model and computer program

International Nuclear Information System (INIS)

DeAngelis, D.L.; Van Winkle, W.; Christensen, S.W.; Blum, S.R.; Kirk, B.L.; Rust, B.W.; Ross, C.

1978-03-01

A generalized fish life-cycle population model and computer program have been prepared to evaluate the long-term effect of changes in mortality in age class 0. The general question concerns what happens to a fishery when density-independent sources of mortality are introduced that act on age class 0, particularly entrainment and impingement at power plants. This paper discusses the model formulation and computer program, including sample results. The population model consists of a system of difference equations involving age-dependent fecundity and survival. The fecundity for each age class is assumed to be a function of both the fraction of females sexually mature and the weight of females as they enter each age class. Natural mortality for age classes 1 and older is assumed to be independent of population size. Fishing mortality is assumed to vary with the number and weight of fish available to the fishery. Age class 0 is divided into six life stages. The probability of survival for age class 0 is estimated considering both density-independent mortality (natural and power plant) and density-dependent mortality for each life stage. Two types of density-dependent mortality are included. These are cannibalism of each life stage by older age classes and intra-life-stage competition

Ergonomic requirements on computer-based information- and handling engineering in nuclear power plants

International Nuclear Information System (INIS)

Fassmann, W.

2002-01-01

This project provides regulatory authorities with a set of criteria for evaluating hybrid man-machine interfaces in nuclear power plant control rooms from a human factors point of view. Such standards are necessary for two reasons: (1) More and more computerised information and control systems have been and will be introduced in nuclear power plant control rooms. One possible result of this trend will be the creation of hybrid man machine interfaces which will provide both conventional and computer-based display and control devices. (2) Available rules and regulations do not contain detailed requirements on how to integrate both types of interface in such a way that plant operation by means of hybrid interfaces will be performed at least as reliably and safely as by means of conventional ones. To fill this gap, criteria and methods were developed which support practical checks of requirements to be applied to hybrid control rooms. This approach is based on state of the art methods and criteria in ergonomics. It makes it possible to analyse and to describe personnel's actions in a consistent and structured way in order to provide the information which is necessary for evaluating human reliability of task performance. Reliability can be evaluated with respect to - accuracy of required information on displays, - networking of tasks, - possibilities of interrupting and cancelling measures which have already been initiated, - possibility to carry out required manuel actions, - level of mental work-strain, - workload level, - probability of erroneous actions. This method is part of a catalogue of recommendations for evaluating hybrid nuclear power plant control rooms. The catalogue also contains recommendations for the design of computerised parts of the man-machine-interface. Application of these design recommendations will help create favourable conditions for an acceptable level of work-strain and for reliable task performance. (orig.) [de

A computational framework for cortical microtubule dynamics in realistically shaped plant cells.

Directory of Open Access Journals (Sweden)

Bandan Chakrabortty

2018-02-01

Full Text Available Plant morphogenesis is strongly dependent on the directional growth and the subsequent oriented division of individual cells. It has been shown that the plant cortical microtubule array plays a key role in controlling both these processes. This ordered structure emerges as the collective result of stochastic interactions between large numbers of dynamic microtubules. To elucidate this complex self-organization process a number of analytical and computational approaches to study the dynamics of cortical microtubules have been proposed. To date, however, these models have been restricted to two dimensional planes or geometrically simple surfaces in three dimensions, which strongly limits their applicability as plant cells display a wide variety of shapes. This limitation is even more acute, as both local as well as global geometrical features of cells are expected to influence the overall organization of the array. Here we describe a framework for efficiently simulating microtubule dynamics on triangulated approximations of arbitrary three dimensional surfaces. This allows the study of microtubule array organization on realistic cell surfaces obtained by segmentation of microscopic images. We validate the framework against expected or known results for the spherical and cubical geometry. We then use it to systematically study the individual contributions of global geometry, cell-edge induced catastrophes and cell-face induced stability to array organization in a cuboidal geometry. Finally, we apply our framework to analyze the highly non-trivial geometry of leaf pavement cells of Arabidopsis thaliana, Nicotiana benthamiana and Hedera helix. We show that our simulations can predict multiple features of the microtubule array structure in these cells, revealing, among others, strong constraints on the orientation of division planes.

A computational framework for cortical microtubule dynamics in realistically shaped plant cells

KAUST Repository

Chakrabortty, Bandan; Blilou, Ikram; Scheres, Ben; Mulder, Bela M.

2018-01-01

Plant morphogenesis is strongly dependent on the directional growth and the subsequent oriented division of individual cells. It has been shown that the plant cortical microtubule array plays a key role in controlling both these processes. This ordered structure emerges as the collective result of stochastic interactions between large numbers of dynamic microtubules. To elucidate this complex self-organization process a number of analytical and computational approaches to study the dynamics of cortical microtubules have been proposed. To date, however, these models have been restricted to two dimensional planes or geometrically simple surfaces in three dimensions, which strongly limits their applicability as plant cells display a wide variety of shapes. This limitation is even more acute, as both local as well as global geometrical features of cells are expected to influence the overall organization of the array. Here we describe a framework for efficiently simulating microtubule dynamics on triangulated approximations of arbitrary three dimensional surfaces. This allows the study of microtubule array organization on realistic cell surfaces obtained by segmentation of microscopic images. We validate the framework against expected or known results for the spherical and cubical geometry. We then use it to systematically study the individual contributions of global geometry, cell-edge induced catastrophes and cell-face induced stability to array organization in a cuboidal geometry. Finally, we apply our framework to analyze the highly non-trivial geometry of leaf pavement cells of Arabidopsis thaliana, Nicotiana benthamiana and Hedera helix. We show that our simulations can predict multiple features of the microtubule array structure in these cells, revealing, among others, strong constraints on the orientation of division planes.

A computational framework for cortical microtubule dynamics in realistically shaped plant cells

KAUST Repository

Chakrabortty, Bandan

2018-02-02

Plant morphogenesis is strongly dependent on the directional growth and the subsequent oriented division of individual cells. It has been shown that the plant cortical microtubule array plays a key role in controlling both these processes. This ordered structure emerges as the collective result of stochastic interactions between large numbers of dynamic microtubules. To elucidate this complex self-organization process a number of analytical and computational approaches to study the dynamics of cortical microtubules have been proposed. To date, however, these models have been restricted to two dimensional planes or geometrically simple surfaces in three dimensions, which strongly limits their applicability as plant cells display a wide variety of shapes. This limitation is even more acute, as both local as well as global geometrical features of cells are expected to influence the overall organization of the array. Here we describe a framework for efficiently simulating microtubule dynamics on triangulated approximations of arbitrary three dimensional surfaces. This allows the study of microtubule array organization on realistic cell surfaces obtained by segmentation of microscopic images. We validate the framework against expected or known results for the spherical and cubical geometry. We then use it to systematically study the individual contributions of global geometry, cell-edge induced catastrophes and cell-face induced stability to array organization in a cuboidal geometry. Finally, we apply our framework to analyze the highly non-trivial geometry of leaf pavement cells of Arabidopsis thaliana, Nicotiana benthamiana and Hedera helix. We show that our simulations can predict multiple features of the microtubule array structure in these cells, revealing, among others, strong constraints on the orientation of division planes.

Detection of regulated herbs and plants in plant food supplements and traditional medicines using infrared spectroscopy.

Science.gov (United States)

Deconinck, E; Djiogo, C A Sokeng; Bothy, J L; Courselle, P

2017-08-05

The identification of a specific toxic or regulated plant in herbal preparations or plant food supplements is a real challenge, since they are often powdered, mixed with other herbal or synthetic powders and compressed into tablets or capsules. The classical identification approaches based on micro- and macroscopy are therefore not possible anymore. In this paper infrared spectroscopy, combined with attenuated total reflectance was evaluated for the screening of plant based preparations for nine specific plants (five regulated and four common plants for herbal supplements). IR and NIR spectra were recorded for a series of self-made triturations of the targeted plants. After pretreatment of the spectral data chemometric classification techniques were applied to both data sets (IR and NIR) separately and the combination of both. The results show that the screening of herbal preparations or plant food supplements for specific plants, using infrared spectroscopy, is feasible. The best model was obtained with the Mid-IR data, using SIMCA as modelling technique. During validation of the model, using an external test set, 21 of 25 were correctly classified and six of the nine targeted plants showed no misclassifications for the selected test set. For the other three a success rate of 50% was obtained. Mid-IR combined with SIMCA can therefore be applied as a first step in the screening of unknown samples, before applying more sophisticated fingerprint approaches or identification tests described in several national and international pharmacopoeia. As a proof of concept five real suspicious samples were successfully screened for the targeted regulated plants. Copyright © 2017 Elsevier B.V. All rights reserved.

An integrated computer-based procedure for teamwork in digital nuclear power plants.

Science.gov (United States)

Gao, Qin; Yu, Wenzhu; Jiang, Xiang; Song, Fei; Pan, Jiajie; Li, Zhizhong

2015-01-01

Computer-based procedures (CBPs) are expected to improve operator performance in nuclear power plants (NPPs), but they may reduce the openness of interaction between team members and harm teamwork consequently. To support teamwork in the main control room of an NPP, this study proposed a team-level integrated CBP that presents team members' operation status and execution histories to one another. Through a laboratory experiment, we compared the new integrated design and the existing individual CBP design. Sixty participants, randomly divided into twenty teams of three people each, were assigned to the two conditions to perform simulated emergency operating procedures. The results showed that compared with the existing CBP design, the integrated CBP reduced the effort of team communication and improved team transparency. The results suggest that this novel design is effective to optim team process, but its impact on the behavioural outcomes may be moderated by more factors, such as task duration. The study proposed and evaluated a team-level integrated computer-based procedure, which present team members' operation status and execution history to one another. The experimental results show that compared with the traditional procedure design, the integrated design reduces the effort of team communication and improves team transparency.

PREPARING FOR EXASCALE: ORNL Leadership Computing Application Requirements and Strategy

Energy Technology Data Exchange (ETDEWEB)

Joubert, Wayne [ORNL; Kothe, Douglas B [ORNL; Nam, Hai Ah [ORNL

2009-12-01

In 2009 the Oak Ridge Leadership Computing Facility (OLCF), a U.S. Department of Energy (DOE) facility at the Oak Ridge National Laboratory (ORNL) National Center for Computational Sciences (NCCS), elicited petascale computational science requirements from leading computational scientists in the international science community. This effort targeted science teams whose projects received large computer allocation awards on OLCF systems. A clear finding of this process was that in order to reach their science goals over the next several years, multiple projects will require computational resources in excess of an order of magnitude more powerful than those currently available. Additionally, for the longer term, next-generation science will require computing platforms of exascale capability in order to reach DOE science objectives over the next decade. It is generally recognized that achieving exascale in the proposed time frame will require disruptive changes in computer hardware and software. Processor hardware will become necessarily heterogeneous and will include accelerator technologies. Software must undergo the concomitant changes needed to extract the available performance from this heterogeneous hardware. This disruption portends to be substantial, not unlike the change to the message passing paradigm in the computational science community over 20 years ago. Since technological disruptions take time to assimilate, we must aggressively embark on this course of change now, to insure that science applications and their underlying programming models are mature and ready when exascale computing arrives. This includes initiation of application readiness efforts to adapt existing codes to heterogeneous architectures, support of relevant software tools, and procurement of next-generation hardware testbeds for porting and testing codes. The 2009 OLCF requirements process identified numerous actions necessary to meet this challenge: (1) Hardware capabilities must be

PREPARING FOR EXASCALE: ORNL Leadership Computing Application Requirements and Strategy

International Nuclear Information System (INIS)

Joubert, Wayne; Kothe, Douglas B.; Nam, Hai Ah

2009-01-01

In 2009 the Oak Ridge Leadership Computing Facility (OLCF), a U.S. Department of Energy (DOE) facility at the Oak Ridge National Laboratory (ORNL) National Center for Computational Sciences (NCCS), elicited petascale computational science requirements from leading computational scientists in the international science community. This effort targeted science teams whose projects received large computer allocation awards on OLCF systems. A clear finding of this process was that in order to reach their science goals over the next several years, multiple projects will require computational resources in excess of an order of magnitude more powerful than those currently available. Additionally, for the longer term, next-generation science will require computing platforms of exascale capability in order to reach DOE science objectives over the next decade. It is generally recognized that achieving exascale in the proposed time frame will require disruptive changes in computer hardware and software. Processor hardware will become necessarily heterogeneous and will include accelerator technologies. Software must undergo the concomitant changes needed to extract the available performance from this heterogeneous hardware. This disruption portends to be substantial, not unlike the change to the message passing paradigm in the computational science community over 20 years ago. Since technological disruptions take time to assimilate, we must aggressively embark on this course of change now, to insure that science applications and their underlying programming models are mature and ready when exascale computing arrives. This includes initiation of application readiness efforts to adapt existing codes to heterogeneous architectures, support of relevant software tools, and procurement of next-generation hardware testbeds for porting and testing codes. The 2009 OLCF requirements process identified numerous actions necessary to meet this challenge: (1) Hardware capabilities must be

Computer aided modeling and expert systems add a needed dimension to water management in power plant operations

International Nuclear Information System (INIS)

Gill, P.H. Jr.

1991-01-01

This paper reports on computer modeling and expert systems applications in water management used to develop appropriate treatment recommendations and monitoring/control functions. Chemical treatment program development in recirculating cooling water (CALGUARD), one-through scale inhibition (THRUGARUD), once through corrosion control (OSCAR), as well as internal boiler water chemistry control (POWER-CHEM), and on-line real time system monitoring (HELMSMAN) plan an increasingly important role in power plant water management practices

A novel computer-aided method to fabricate a custom one-piece glass fiber dowel-and-core based on digitized impression and crown preparation data.

Science.gov (United States)

Chen, Zhiyu; Li, Ya; Deng, Xuliang; Wang, Xinzhi

2014-06-01

Fiber-reinforced composite dowels have been widely used for their superior biomechanical properties; however, their preformed shape cannot fit irregularly shaped root canals. This study aimed to describe a novel computer-aided method to create a custom-made one-piece dowel-and-core based on the digitization of impressions and clinical standard crown preparations. A standard maxillary die stone model containing three prepared teeth each (maxillary lateral incisor, canine, premolar) requiring dowel restorations was made. It was then mounted on an average value articulator with the mandibular stone model to simulate natural occlusion. Impressions for each tooth were obtained using vinylpolysiloxane with a sectional dual-arch tray and digitized with an optical scanner. The dowel-and-core virtual model was created by slicing 3D dowel data from impression digitization with core data selected from a standard crown preparation database of 107 records collected from clinics and digitized. The position of the chosen digital core was manually regulated to coordinate with the adjacent teeth to fulfill the crown restorative requirements. Based on virtual models, one-piece custom dowel-and-cores for three experimental teeth were milled from a glass fiber block with computer-aided manufacturing techniques. Furthermore, two patients were treated to evaluate the practicality of this new method. The one-piece glass fiber dowel-and-core made for experimental teeth fulfilled the clinical requirements for dowel restorations. Moreover, two patients were treated to validate the technique. This novel computer-aided method to create a custom one-piece glass fiber dowel-and-core proved to be practical and efficient. © 2013 by the American College of Prosthodontists.

Fast diagnosis and treatment of cracklike defect injuriousness in PWR power plant equipment

International Nuclear Information System (INIS)

Benchimol, M.; Boneh, B.; Gilles, P.

1983-08-01

Defects detected in nuclear power plant components in the course of periodic inspections may have been formed during fabrication, at installation or in service. In order to accelerate decision-making subsequent to defect detection and increase the effectiveness of inspection programs, it is proposed in this paper that a package be prepared for each main system at the design stage to permit immediate diagnosis of defect injuriousness and to offer guidelines for mitigating action. The paper comprises: description of such a package, hereafter referred to as ''Defect Injuriousness Diagnosis and Treatment Package'' (DIDTP); breakdown of a DIDTP and demonstration of the computational methods used in its elaboration; presentation of the computer codes (ANODE, TITAN) used for automatic compilation of DIDTP's; example of DIDTP application

[Function of transport H+-ATPases in plant cell plasma and vacuolar membranes of maize under salt stress conditions and effect of adaptogenic preparations].

Science.gov (United States)

Rybchenko, Zh I; Palladina, T O

2011-01-01

Participations of electrogenic H+-pumps of plasma and vacuolar membranes represented by E1-E2 and V-type H+-ATPases in plant cell adaptation to salt stress conditions has been studied by determination of their transport activities. Experiments were carried out on corn seedlings exposed during 1 or 10 days at 0.1 M NaCl. Preparations Methyure and Ivine were used by seed soaking at 10(-7) M. Plasma and vacuolar membrane fractions were isolated from corn seedling roots. In variants without NaCl a hydrolytical activity of plasma membrane H+-ATPase was increased with seedling age and its transport one was changed insignificantly, wherease the response of the weaker vacuolar H+-ATPase was opposite. NaCl exposition decreased hydrolytical activities of both H+-ATPases and increased their transport ones. These results demonstrated amplification of H+-pumps function especially represented by vacuolar H+-ATPase. Both preparations, Methyure mainly, caused a further increase of transport activity which was more expressed in NaCl variants. Obtained results showed the important role of these H+-pumps in plant adaptation under salt stress conditions realized by energetical maintenance of the secondary active Na+/H+ -antiporters which remove Na+ from cytoplasm.

A computer - aided system for the the E.D.F. 1400 MW. Nuclear power plants control

International Nuclear Information System (INIS)

Beltranda, G.; Philipps, C.

1988-01-01

The future E.D.F. 1400 MW nuclear power plants (due to be commissioned in 1991 at CHOOZ) are provided with a control and instrumentation system including the following levels: - sensors and actuators (LEVEL 0): this is the interface of the elementary acquisition and control signals; - the programmable logical and numerical controllers (LEVEL 1) for the logical control sequences and analog adjustment sequences for the whole equipment of the facilities; - the control room (LEVEL 2) including the computer-aided operation system as well as the wall mimic diagram and the auxiliary panel directly connected to the controllers. This is the processing and control conversational level; - the maintenance and site computer-aided systems (LEVEL 3). This paper aims at describing the computer-aided operation system (called KIC N4), its main functions, its architecture and the solutions retained as regards its softwares and the high-quality of data required. The achievement of this system has been entrusted by EDF to the SEMA. METRA/CIMSA-SINTRA grouping, among which SEMA.METRA is the leading company

COMMIX-PPC: A three-dimensional transient multicomponent computer program for analyzing performance of power plant condensers

International Nuclear Information System (INIS)

Chien, T.H.; Domanus, H.M.; Sha, W.T.

1993-02-01

The COMMIX-PPC computer pregrain is an extended and improved version of earlier COMMIX codes and is specifically designed for evaluating the thermal performance of power plant condensers. The COMMIX codes are general-purpose computer programs for the analysis of fluid flow and heat transfer in complex Industrial systems. In COMMIX-PPC, two major features have been added to previously published COMMIX codes. One feature is the incorporation of one-dimensional equations of conservation of mass, momentum, and energy on the tube stile and the proper accounting for the thermal interaction between shell and tube side through the porous-medium approach. The other added feature is the extension of the three-dimensional conservation equations for shell-side flow to treat the flow of a multicomponent medium. COMMIX-PPC is designed to perform steady-state and transient. Three-dimensional analysis of fluid flow with heat transfer tn a power plant condenser. However, the code is designed in a generalized fashion so that, with some modification, it can be used to analyze processes in any heat exchanger or other single-phase engineering applications. Volume I (Equations and Numerics) of this report describes in detail the basic equations, formulation, solution procedures, and models for a phenomena. Volume II (User's Guide and Manual) contains the input instruction, flow charts, sample problems, and descriptions of available options and boundary conditions

Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-01-01

Computer codes are widely used in Member States for the analysis of safety at nuclear power plants (NPPs). Coupling of computer codes, a further tool for safety analysis, is especially beneficial to safety analysis. The significantly increased capacity of new computation technology has made it possible to switch to a newer generation of computer codes, which are capable of representing physical phenomena in detail and include a more precise consideration of multidimensional effects. The coupling of advanced, best estimate computer codes is an efficient method of addressing the multidisciplinary nature of reactor accidents with complex interfaces between disciplines. Coupling of computer codes is very advantageous for studies which relate to licensing of new NPPs, safety upgrading programmes for existing plants, periodic safety reviews, renewal of operating licences, use of safety margins for reactor power uprating, better utilization of nuclear fuel and higher operational flexibility, justification for lifetime extensions, development of new emergency operating procedures, analysis of operational events and development of accident management programmes. In this connection, the OECD/NEA Working Group on the Analysis and Management of Accidents (GAMA) recently highlighted the application of coupled computer codes as an area of 'high collective interest'. Coupled computer codes are being developed in many Member States independently or within small groups composed of several technical organizations. These developments revealed that there are many types and methods of code coupling. In this context, it was believed that an exchange of views and experience while addressing these problems at an international meeting could contribute to the more efficient and reliable use of advanced computer codes in nuclear safety applications. The present publication constitutes the report on the Technical Meeting on Progress in the Development and Use of Coupled Codes for Accident

Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-01-01

Computer codes are widely used in Member States for the analysis of safety at nuclear power plants (NPPs). Coupling of computer codes, a further tool for safety analysis, is especially beneficial to safety analysis. The significantly increased capacity of new computation technology has made it possible to switch to a newer generation of computer codes, which are capable of representing physical phenomena in detail and include a more precise consideration of multidimensional effects. The coupling of advanced, best estimate computer codes is an efficient method of addressing the multidisciplinary nature of reactor accidents with complex interfaces between disciplines. Coupling of computer codes is very advantageous for studies which relate to licensing of new NPPs, safety upgrading programmes for existing plants, periodic safety reviews, renewal of operating licences, use of safety margins for reactor power uprating, better utilization of nuclear fuel and higher operational flexibility, justification for lifetime extensions, development of new emergency operating procedures, analysis of operational events and development of accident management programmes. In this connection, the OECD/NEA Working Group on the Analysis and Management of Accidents (GAMA) recently highlighted the application of coupled computer codes as an area of 'high collective interest'. Coupled computer codes are being developed in many Member States independently or within small groups composed of several technical organizations. These developments revealed that there are many types and methods of code coupling. In this context, it was believed that an exchange of views and experience while addressing these problems at an international meeting could contribute to the more efficient and reliable use of advanced computer codes in nuclear safety applications. The present publication constitutes the report on the Technical Meeting on Progress in the Development and Use of Coupled Codes for Accident

T Plant Overpack Tiedown Analysis

International Nuclear Information System (INIS)

RILEY, D.L.

2000-01-01

This tiedown evaluation meets the requirement imposed by HNF-6550, ''Safety Evaluation for Packaging (Onsite) T Plant Canyon Items,'' (O'Brien 2000). O'Brien (2000) requires that any items prepared for shipment from T Plant to the burial grounds

Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

Energy Technology Data Exchange (ETDEWEB)

Cho, Hyo Sung [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; Woo, Tae Ho [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; The Cyber Univ. of Korea, Seoul (Korea, Republic of). Dept. of Mechanical and Control Engineering

2017-03-15

The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

International Nuclear Information System (INIS)

Cho, Hyo Sung; Woo, Tae Ho; The Cyber Univ. of Korea, Seoul

2017-01-01

The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

BWR plant analyzer development at BNL

International Nuclear Information System (INIS)

Cheng, H.S.; Wulff, W.; Mallen, A.N.; Lekach, S.V.; Stritar, A.; Cerbone, R.J.

1985-01-01

Advanced technology for high-speed interactive nuclear power plant simulations is of great value for timely resolution of safety issues, for plant monitoring, and for computer-aided emergency responses to an accident. Presented is the methodology employed at BNL to develop a BWR plant analyzer capable of simulating severe plant transients at much faster than real-time process speeds. Five modeling principles are established and a criterion is given for selecting numerical procedures and efficient computers to achieve the very high simulation speeds. Typical results are shown to demonstrate the modeling fidelity of the BWR plant analyzer

C.A.S.H. - a transient integrated plant model for a HTR-module power plant. User manual

International Nuclear Information System (INIS)

Biesenbach, R.; Lauer, A.; Struth, S.

1997-07-01

The computer code C.A.S.H. has been developed as an integrated plant model for the HTR-Module reactor, in order to treat safety related questions about this type of power plant which require a detailed numeric simulation of the transient behaviour of the integrated plant. The present report contains the user manual for this plant model. It consists of three parts: In the first part, the code structure and functions, the course of the simulation calculations, and important code parts are described. The second part is devoted to the practical application and explains extensively the handling of the complex code system with several sample calculations. These computing cases comprise load-follow transients and the shutdown procedure of the HTR-Module and are presented and discussed with the full input data, job patterns, and numerous computer graphics. The third part contains the input manual of C.A.S.H. and is rather extensive as it includes the complete inputs of several reactor component computer codes along with the control program of the integrated plant model. (orig./DG) [de

Computational Viscoelasticity

CERN Document Server

Marques, Severino P C

2012-01-01

This text is a guide how to solve problems in which viscoelasticity is present using existing commercial computational codes. The book gives information on codes’ structure and use, data preparation  and output interpretation and verification. The first part of the book introduces the reader to the subject, and to provide the models, equations and notation to be used in the computational applications. The second part shows the most important Computational techniques: Finite elements formulation, Boundary elements formulation, and presents the solutions of Viscoelastic problems with Abaqus.

Computational implementation of a systems prioritization methodology for the Waste Isolation Pilot Plant: A preliminary example

Energy Technology Data Exchange (ETDEWEB)

Helton, J.C. [Arizona State Univ., Tempe, AZ (United States). Dept. of Mathematics; Anderson, D.R. [Sandia National Labs., Albuquerque, NM (United States). WIPP Performance Assessments Departments; Baker, B.L. [Technadyne Engineering Consultants, Albuquerque, NM (United States)] [and others

1996-04-01

A systems prioritization methodology (SPM) is under development to provide guidance to the US DOE on experimental programs and design modifications to be supported in the development of a successful licensing application for the Waste Isolation Pilot Plant (WIPP) for the geologic disposal of transuranic (TRU) waste. The purpose of the SPM is to determine the probabilities that the implementation of different combinations of experimental programs and design modifications, referred to as activity sets, will lead to compliance. Appropriate tradeoffs between compliance probability, implementation cost and implementation time can then be made in the selection of the activity set to be supported in the development of a licensing application. Descriptions are given for the conceptual structure of the SPM and the manner in which this structure determines the computational implementation of an example SPM application. Due to the sophisticated structure of the SPM and the computational demands of many of its components, the overall computational structure must be organized carefully to provide the compliance probabilities for the large number of activity sets under consideration at an acceptable computational cost. Conceptually, the determination of each compliance probability is equivalent to a large numerical integration problem. 96 refs., 31 figs., 36 tabs.

Computational implementation of a systems prioritization methodology for the Waste Isolation Pilot Plant: A preliminary example

International Nuclear Information System (INIS)

Helton, J.C.

1996-04-01

A systems prioritization methodology (SPM) is under development to provide guidance to the US DOE on experimental programs and design modifications to be supported in the development of a successful licensing application for the Waste Isolation Pilot Plant (WIPP) for the geologic disposal of transuranic (TRU) waste. The purpose of the SPM is to determine the probabilities that the implementation of different combinations of experimental programs and design modifications, referred to as activity sets, will lead to compliance. Appropriate tradeoffs between compliance probability, implementation cost and implementation time can then be made in the selection of the activity set to be supported in the development of a licensing application. Descriptions are given for the conceptual structure of the SPM and the manner in which this structure determines the computational implementation of an example SPM application. Due to the sophisticated structure of the SPM and the computational demands of many of its components, the overall computational structure must be organized carefully to provide the compliance probabilities for the large number of activity sets under consideration at an acceptable computational cost. Conceptually, the determination of each compliance probability is equivalent to a large numerical integration problem. 96 refs., 31 figs., 36 tabs

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

Development of nuclear power plant management system for Kyushu Electric Power Co., Inc

International Nuclear Information System (INIS)

Nakamura, Kenichi; Akiyoshi, Tatsuo; Tanimoto, Kazuo; Ogura, Kazuhito; Ibi, Yuji; Kawasaki, Michiyuki

2002-01-01

The Kyushu Electric Power Co., Ltd. progresses development of the nuclear power plant management system using IT under aims at upgrading of efficiency, level, and reliability on maintenance and administration business under five years planning since 1999 fiscal year. The outline of the system are explained in this paper. As a result of preparation on power station net work and personal computers set in all of company, an environment capable of using these infrastructures and introducing large scale systems on transverse business over every groups of each power station could be established. (G.K.)

7 CFR 1126.7 - Pool plant.

Science.gov (United States)

2010-01-01

... excluded from the supply plant's shipments in computing the plant's shipping percentage. (d) A plant... part, or the plant has automatic pooling status under the other Federal order; and (7) That portion of...

How-To-Do-It: Using Cauliflower to Demonstrate Plant Tissue Culture.

Science.gov (United States)

Haldeman, Janice H.; Ellis, Jane P.

1988-01-01

Presents techniques used for disinfestation of plant material, preparation of equipment and media, and laboratory procedures for tissue culture using cauliflower. Details methods for preparing solutions and plant propagation by cloning. (CW)

Cone-beam computed tomography analysis of the apical third of curved roots after mechanical preparation with different automated systems

International Nuclear Information System (INIS)

Oliveira, Cesar Augusto Pereira; Pascoalato, Cristina; Meurer, Maria Ines; Silva, Silvio Rocha Correa

2009-01-01

The present study evaluated by cone-beam computed tomography (CBCT) the apical canal transportation and centralizing ability of different automated systems after root canal preparation. The mesiobuccal canals of maxillary first molars (n=10 per group) were prepared with: GI - reciprocating system with K-Flexofile; GII - reciprocating system with NiTiFlex files; GIII - rotary system with K3 instruments; GIV - rotary system with RaCe instruments. CBCT scans were taken before and after biomechanical preparation up to a 40.02 diameter. Canal transportation was determined by measuring the smallest distance between the inner canal walls and the mesial and distal sides of the root. The centralization ability corresponded to the difference between the measurements from transportation evaluation, using the linear voxel to voxel method of analysis. The mean transportation was 0.06 ± 0.14 mm, with a tendency to deviate to the mesial side of the root (n=22), with no statistically significant difference among the groups (p=0.4153). The mean centralization index was 0.15 ± 0.65 also without statistically significant difference among the groups (p=0.0881). It may be concluded that apical canal transportation and centralization ability were not influenced by the type of mechanical movement and instruments used. (author)

Cone-beam computed tomography analysis of the apical third of curved roots after mechanical preparation with different automated systems

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Oliveira, Cesar Augusto Pereira; Pascoalato, Cristina [University of Southern Santa Catarina (UNISUL), Tubarao, SC (Brazil); Meurer, Maria Ines [Federal University of Santa Catarina (UFSC), Florianopolis, SC (Brazil); Silva, Silvio Rocha Correa, E-mail: silvio@foar.unesp.b [Sao Paulo State University (UNESP), Araraquara, SP (Brazil)

2009-07-01

The present study evaluated by cone-beam computed tomography (CBCT) the apical canal transportation and centralizing ability of different automated systems after root canal preparation. The mesiobuccal canals of maxillary first molars (n=10 per group) were prepared with: GI - reciprocating system with K-Flexofile; GII - reciprocating system with NiTiFlex files; GIII - rotary system with K3 instruments; GIV - rotary system with RaCe instruments. CBCT scans were taken before and after biomechanical preparation up to a 40.02 diameter. Canal transportation was determined by measuring the smallest distance between the inner canal walls and the mesial and distal sides of the root. The centralization ability corresponded to the difference between the measurements from transportation evaluation, using the linear voxel to voxel method of analysis. The mean transportation was 0.06 +- 0.14 mm, with a tendency to deviate to the mesial side of the root (n=22), with no statistically significant difference among the groups (p=0.4153). The mean centralization index was 0.15 +- 0.65 also without statistically significant difference among the groups (p=0.0881). It may be concluded that apical canal transportation and centralization ability were not influenced by the type of mechanical movement and instruments used. (author)

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